ORNL-1154
AIRCRAFT NUCLEAR PROPULSION PROJECT
QUARTERLY PROGRESS REPORT
For Period Ending September 10, 1951
SUMMARY
1
Part I. REACTOR THEORY AND DESIGN
1. THE AIRCRAFT REACTOR EXPERIMENT
Core Design
Fluid Circuit
Heat-disposal circuit
Contamination of helium system
Control of the ARE
Liquid-fuel control system
Solid absorber rod design
Electronic computor design
Electrical Circuit
Remote-Handling Equipment
Building Facility for the ARE
9
9
10
10
10
11
11
11
12
12
12
12
2. EXPERIMENTAL REACTOR ENGINEERING
Liquid-Fuel Systems
Pump Development
Centrifugal pumps for figure-eight loops
ARE pump design
Canned-rotor pump
Level tank pump
Electromagnetic pumps
Test Loops
Calibration loop
Sodium manometer loop
Seal Tests
Frozen-sodium seal
Bellows seal
Graphitar and tool steel seal
Instrumentation
Stress-Rupture Tests
Self-Welding Tests
Valve-Packing Experiments
Contamination of Liquid-Metal Systems
Cleaning of liquid-metal systems
Purification of liquid metals
Purification of inert gases
Analytical results with sodium
Investigation of Sodium Condensation
ARE Component Tests
Heat-Exchanger Tests
Building Modifications and Experimental Facilities
Alkali Metals Manual
14
14
15
15
16
17
17
17
20
20
20
20
21
21
21
23
23
24
24
25
25
26
26
26
27
27
28
28
30
3. REACTOR PHYSICS
31
IBM Calculations
Production report
The multiregion reactor problem
Cylindrical multigroup calculation
The effect of the boron blanket in the ANP reactor
Statics of the Aircraft Reactor Experiment
Summary of calculations on the ARE
Estimated critical mass of the ARE
Control rod effectiveness
Kinetics of the Aircraft Reactor Experiment
Mass-reactivity coefficient
Fuel conductivity
Neutron lifetime
Start-up accident
Coolant temperature
Preparatory Physics Calculations
Correction to "Wigner formula for resonance escape" probability
Effect of "Wigner formula for resonance escape" correction
The transmission coefficient of the B4C curtain in the ANP and ARE reactors
Heating in the boron carbide curtain in the ANP reactor
Temperature savings in the ANP reactor
The Sodium Hydroxide Reactor
4. CRITICAL EXPERIMENTS
Critical Assembly of Air-Water Reactor
Critical Assembly of Graphite Reactor
32
32
33
33
33
34
34
36
37
48
49
49
56
56
56
60
60
64
66
66
67
70
79
79
80
Part II. SHIELDING RESEARCH
5. BULK SHIELDING REACTOR
Reactor Operation
Mock-Up of the Unit Shield
Mock-Up of the Divided Shield
83
83
83
83
6. LID TANK
87
7. DUCT TEST
89
8. SHIELDING CALCULATIONS
Analysis of Bulk Shielding Reactor Neutron Data
Interpretation of Lid Tank Gamma-Ray Data
Shielding Calculations for the ARE
Activation of nitrogen and helium in the ARE reactor pit
Activation of impurities in BeO
Detection of leaks in the fuel elements by means of radioactive tracers
NDA Divided-Shield Studies
Use of NH3 as a Shielding Material
Mechanical requirements of an ammonia shield
Calculational procedure
Comparison of shield weights using NH3 and H2O
91
91
92
92
92
93
93
93
94
95
95
96
9. NUCLEAR MEASUREMENTS
The 5-Mev Van de Graaff Accelerator
Measurement of the (n,2n) Reaction in Beryllium
Bremsstrahlung from 8Li
Radiation detection equipment
97
97
97
98
98
Bremsstrahlung activity
Time-of-Flight Neutron Spectrometer
98
100
Part III. MATERIALS RESEARCH
10. CORROSION RESEARCH
Static Corrosion by Fluoride Fuels
The pretreatment process
Corrosion of structural metals
Corrosion of platinum
Static Corrosion by Moderator Coolants
Capsule technique with hydroxides
Corrosion by sodium hydroxide
Corrosion by potassium hydroxide
Corrosion by other hydroxides
Corrosion by binary hydrogenous systems
Static Corrosion by Fluoride Coolant Mixtures
Static Corrosion by Sodium
Static Corrosion Test of a Reactor System
Mass Transfer Phenomenon in Static Corrosion
Chemical-reaction mechanism for mass transfer
Experimental evidence
Dynamic Corrosion Tests in Thermal-Convection Loops
Corrosion by lithium and lead
Corrosion by sodium
Dynamic Corrosion Tests in Forced-Convection Loops
103
104
104
106
110
112
113
113
113
118
118
118
118
122
122
122
123
124
124
129
131
11. PHYSICAL PROPERTIES AND HEAT-TRANSFER RESEARCH
Investigation of Free Convection Within Liquid-Fuel Elements
Theoretical analysis of natural convection
Measurement of the fuel-element temperature distribution
Measurement of the fuel-element velocity distribution
Physical Properties
Heat capacity
Thermal conductivity of liquids
Thermal conductivity of solids
Falling-ball viscometer
Brookfield viscometer
Vapor pressure
Density
Heat-Transfer Coefficients
Heat transfer in fused hydroxides and salts
Heat transfer in boiling-liquid-metal systems
Heat transfer in molten lithium
132
132
132
133
134
134
134
135
135
136
136
136
137
137
137
138
139
12. METALLURGY AND CERAMICS
Welding of Inconel
Tensile tests
Fatigue tests
All-weld-metal tensile tests
Corrosion of welds
Special weld tests
Welding of Molybdenum
Creep of Metals in Controlled Atmospheres
Creep of 316 stainless steel
Creep of Inconel
141
141
141
143
144
145
145
145
145
146
146
Creep of niobium
Creep test of loaded inconel tube
Stress-Relaxation Tests
Fuel-Element Fabrication
Hot rolling
Mechanically formed matrix
Loose-powder sintering
Rubberstatic pressing
Compatibility of potential fuel-element materials
Control-Rod Fabrication
Metal Cladding of Beryllium Oxide
Refractory Metals
Ceramics Laboratory
146
146
147
147
147
149
149
149
151
151
152
152
152
13. CHEMISTRY OF HIGH-TEMPERATURE LIQUIDS
Fuel Development
Low-melting fluoride systems
Preparation of UF3
Homogeneous fuels
Moderator-Coolant Development
Preparation of pure sodium hydroxide
Preparation of other hydroxides
Decomposition pressures of hydroxides
Binary hydroxide systems
Hydroxide-fluoride systems
Hydroxide-borate systems
Coolant Development
154
154
155
159
161
162
162
165
165
166
167
168
168
14. RADIATION DAMAGE
Creep Under Irradiation
Radiation Effects on Thermal Conductivity
Irradiation of Fluoride Fuels
Pile irradiation of fuel capsules
Cyclotron irradiation of fuel capsules
Corrosion of Iron by Lithium Under Cyclotron Irradiation
Liquid Metals In-Pile Loop
170
170
171
173
173
173
174
174
Part IV. ALTERNATE SYSTEMS
15. SUPERCRITICAL WATER REACTOR
Outline of a Specific Design
Fuel Elements and Assemblies
Reactivity
Stability
Pressure Shell
Shield
179
179
180
180
182
183
183
16. CIRCULATING-MODERATOR-COOLANT REACTOR: HKF
Operational Characteristics
Reactor Characteristics
Core Design
Reactor Physics
185
185
186
186
187
17. CIRCULATING-MODERATOR-COOLANT REACTOR: ORNL
Fluid-Circuit Specifications
Fuel-Element Design
188
188
188
Reactor Design
188
18. HIGH-TEMPERATURE POWER PLANT STUDIES
Sodium-Liquid-Vapor Compressor Jet
Helium-Cooled Reactors
192
193
194
Part V. APPENDIXES
19. ANALYTICAL CHEMISTRY
Analysis of Reactor Fuels
Spectrographic results
Development of colorimetric methods
Determination of platinum
Oxygen in Sodium
Oxygen in Lead
Oxygen in Helium
Oxygen and Nitrogen in Lithium
Carbon in Lithium
Uranium Trifluoride in Uranium Tetrafluoride
Identification of Residue in Lithium-Metal Coolant System
Analytical Services
199
200
200
200
201
201
201
201
202
202
202
203
204
20. LIST OF REPORTS ISSUED
205
ORNL-1170
AIRCRAFT NUCLEAR PROPULSION PROJECT
QUARTERLY PROGRESS REPORT
For Period Ending December 10, 1951
FOREWORD
1
PART I REACTOR THEORY AND DESIGN
SUMMARY AND INTRODUCTION
5
1. CIRCULATING-FUEL AIRCRAFT REACTOR
Airplane and Overall Arrangement
Reactor
Engine
Radiators
Shielding
Accessory Systems
7
7
8
8
9
9
9
2. LIQUID-METAL-COOLED AIRCRAFT REACTOR EXPERIMENT
Core-Reflector-Pressure Shell
Fluid Circuit
Reactor Control
Control system
High temperature fission chamber
Reactor dynamic computer
Instrumentation
ARE Building Facility
Remote-Handing Equipment
11
11
11
11
12
12
12
12
12
12
3. REACTOR PHYSICS
Reactor Calculations on IBM Equipment
Circulating-Fuel Reactors
Beryllium-oxide moderated reactor
Water-moderated reactor
Comparison of H2O- and BeO-moderated reactors
Effect of delayed neutrons on kinetic response
Circulating-Moderator Reactors
Errors in Reactor Physics Calculations
13
13
14
14
17
29
30
31
31
4. CRITICAL EXPERIMENTS
Preliminary Assembly of Direct-Cycle Reactor
Graphite Reactor
35
35
37
5. NUCLEAR MEASUREMENTS
The 5-MeV Van de Graaff Accelerator
Measurements of the (n,2n) Reaction in Beryllium
Time-of-Flight Neutron Spectrometer
38
38
38
39
6. EXPERIMENTAL REACTOR ENGINEERING
Pump Development
Centrifugal pumps for figure-eight loops
ARE centrifugal pump design
Canned-rotor pump
Frozen-sodium-seal pump
Two-stage electromagnetic pump
Electromagnetic pump cell development
Seal Tests
Frozen-sodium seal
Frozen-fluoride seal
Graphitar ring-ketos tool steel gas seal
Test Loops
Calibration loop
Sodium manometer loop
Self-welding tests
Materials tests
Valve tests
Heat-Exchanger Tests
NaK to NaK heat exchanger
Sodium to air radiator
Liquid-Fuel Systems
Instrumentation
Level control and indication
Flow measurement
Pressure-measuring devices
Full-Scale ARE Component Test Facilities
Fluoride Production
Cleaning of Fluorides from Systems
NaK Disposal
Alkali Metals Manual
40
40
41
41
42
42
42
42
43
43
43
43
44
44
44
44
44
45
45
45
47
47
47
48
48
48
48
49
49
50
50
PART II SHIELDING RESEARCH
SUMMARY AND INTRODUCTION
53
7. BULK SHIELDING REACTOR
Reactor Operation
Mockup of the Unit Shield
Mockup of the Divided Shield
54
54
55
59
8. DUCT TESTS
Air-Filled Duct Tests in Lid Tank
Cylindrical ducts
Annular ducts
Liquid-Metal Duct Test in Thermal Column
65
65
65
72
72
9. SHIELDING INVESTIGATIONS
Tower Shielding Facility Proposal
Circulating-Fuel Reactor Shields
NDA Divided-Shield Studies
73
73
74
74
PART III MATERIALS RESEARCH
SUMMARY AND INTRODUCTION
77
10. CHEMISTRY OF HIGH-TEMPERATURE LIQUIDS
Low Melting-Fluoride Fuel Systems
LiF-KF-UF4
LiF-NaF-KF-UF4
LiF-NaF-RbF-UF4
NaF-BeF2-UF4
LiF-NaF-BeF2-UF4
Ionic Species in Fused Fluorides
Experimental procedures
Results of electrolyses
Homogeneous Fuels
Uranium solubility in hydroxide-borate mixtures
Uranium solubility in hydroxides with various additives
Moderator-Coolant Development
Preparation of pure hydroxides
KOH-LiOH
Hydroxide-fluoride systems
Coolant Development
RbF-LiF
NaF-BeF2
NaF-KF-RbF
KF-LiF-RbF
NaF-LiF-RbF
Ternary systems containing BeF2
Service Functions
79
79
80
80
80
81
81
82
82
82
83
83
83
84
84
85
85
85
85
86
86
86
86
87
87
11. CORROSION RESEARCH
Static Corrosion by Fluorides
Static Corrosion by Hydroxides
Corrosion of uncoated metals
Corrosion of coated metals
Dissolution of metals in sodium hydroxide
Static Corrosion by Fluoride-Hydroxide Systems
Static Corrosion by Sodium Cyanide
Static Corrosion by Liquid Metals
Sodium on stainless steel
Lithium on coated stainless steel
Static Corrosion of Fuel Capsules in Sodium
Dynamic Corrosion in Thermal Convection Loops
Fluoride corrosion
Hydroxide corrosion
Fundamental Corrosion Research
EMF measurements in hydroxides
Polarographic study of sodium hydroxide
Survey of the mass-transfer phenomena
88
89
89
90
98
100
102
103
103
103
103
105
106
107
107
110
110
110
111
12. HEAT-TRANSFER RESEARCH AND PHYSICAL PROPERTIES
Natural Convection in Liquid-Fuel Elements
Heat-Transfer Coefficients
Heat transfer in fused hydroxides and salts
Heat transfer in molten lithium
115
115
116
116
117
Entrance-region heat transfer in a sodium system
Heat transfer in a circulating fuel system
Heat Capacity
Thermal Conductivity
Thermal conductivity of liquids
Thermal conductivity of solids
Thermal conductivity of diatomaceous silica powder
Density of Liquids
Viscosity
Falling-ball viscometer
Zahn type viscometer
Viscosity of fluoride mixtures
Vapor Pressure of Liquid Fuels
118
120
120
120
120
122
122
123
123
124
124
126
126
13. METALLURGY AND CERAMICS
128
Solid-Fuel-Element Fabrication
Effect of UO2 particle size
Effect of rolling temperature
Effect of elimination of capsule
Preparation of tubular fuel elements
Welding Techniques
Cone arc welding
Resistance welding
Brazing Techniques
Effect of brazing time
Brazing of clad fuel elements
Nickel-palladium brazing alloy
Creep and Stress Rupture of Metals
Operation of creep and stress-rupture equipment
Creep-rupture tests of Inconel
Creep of nickel Z
Stress-rupture tests
Ceramics Laboratory
Equipment
Subcontract work
128
129
130
130
132
132
132
132
135
135
135
135
137
138
139
140
140
141
141
141
14. RADIATION DAMAGE
Irradiation of Fused Materials
Pile irradiation of fuel and KOH capsules
Cyclotron irradiation of fuel and KOH capsules
In-Pile Circulating Loops
Creep Under Irradiation
Radiation Effects on Thermal Conductivity
142
142
142
143
144
144
145
PART IV APPENDIXES
SUMMARY AND INTRODUCTION
149
15. SUPERCRITICAL-WATER REACTOR
Analysis of Supercritical Water Reactor by NDA
Stability
Start-up
Analysis of Supercritical-Water Reactor by ORNL
Compressor-jet cycle
Results
150
150
150
150
151
151
151
16. ANALYTICAL CHEMISTRY
Studies of Diatomaceous Earth
Determination of Ni, NiO, and O in Alkali Hydroxides
Available oxygen
Metallic nickel
Nickel oxide
Studies of Ternary Alkali Fluoride Eutectic
pH of aqueous solutions of alkali fluorides
Composition of the eutectic
Metallic impurities
Corrosion of Metal Containers by Hydroxide Solutions
Determination of Uranium Trifluoride
Determination of Oxygen in NaK
Determination of Oxygen in Helium
Preparation of Oxygen-Free Sodium Samples
Clarity of Borated Water in Concrete Tanks
Analytical Services
152
152
153
153
153
153
154
154
155
155
155
155
155
156
156
157
157
17. LIST OF REPORTS ISSUED
158
18. DIRECTORY OF ACTIVE ANP RESEARCH PROJECTS AT ORNL
Reactor and Component Design
Shielding Research
Materials Research
Analysis of Other Nuclear Reactor Systems
161
161
164
165
172
19. TECHNICAL ORGANIZATION OF THE ANP PROJECT
173
ORNL-1227
AIRCRAFT NUCLEAR PROPULSION PROJECT
QUARTERLY PROGRESS REPORT
For Period Ending March 10, 1952
FOREWORD
1
PART I. REACTOR THEORY AND DESIGN 3 SUMMARY AND INTRODUCTION 5 1. CIRCULATINGFUEL AIRCRAFT REACTOR
7
Reactor with Tandem Heat Exchangers
7
Reactor with Annular Heat Exchangers
9
Reactor Shield Designs 9
Design procedure 9 Activation of the secondary coolant 11 Shield weights and specifications
11
2, CIRCULATING-FUEL AIRCRAFT REACTOR EXPERIMENT
13
Core Design
13
Primary coolant circuit 15 Secondary coolant circuit 15 Core temperature distribution
16
External Fluid Circuit
16
Pumps 16 Heat exchangers 18 Primary coolant system 18 Secondary coolant system 18 Monitoring circuit 18
Preheating System
18
Reactor assembly 19
Piping ~
19
Heat exchangers ~~
19
Electrical Power Circuits 19,
Control System 20
Shim control
20
Regulating and safety rods 20
High-temperature fission chamber 21 Control console and panel 21 Reactor dynamic computer
Instrumentation 21
Building 22
21
3. EXPERIMENTAL REACTOR ENGINEERING 23
Seals and Closures
23
Frozen sodium seal 24
Frozen fluoride seal 24
Bellows type of face seal for ARE pump 24
Stuffing-box seals for molten fluorides 25
Lubrication of seals and shafts
26
Pumps 26
ARE centrifugal pump 26 Laboratory frozen-fluoride-sealed centrifugal pump 27 Worthite frozen-sodium-sealed
pump 27 Modified Durco centrifugal pumps 27 Forced-convection-cooled sodium-sealed pumps 29 Canned-rotor
pumps 29
Valves 29
Packing-gland seal test equipment 29
i
o
Frozen fluorides valve 30 Ball check valves 30 Valve seat test 30
Heat Exchangers 30
Aircraft type of radiator 30 Sodium-to-air radiator 31 Fluoride-to-fluoride heat exchanger 31 NaK-to-NaK heat
exchanger 32 -Heat transfer in circulating fluoride loops
32
Instrumentation 33 Flow measurement 33 Pressure measurement 34 Temperature measurement 34 Level controls
and level indicators
34
Heating and Cooling of High-Temperature Systems 35 External heating systems 35 Induction heating 36 Resistance
heating 36 Insulation testing 36 ARE core preheating 37
Technology of High-Temperature Liquids 37
Fluoride preparation and handling 37 Sampling and analyzing techniques 39 Diffusivity of helium through stainless
steel 39 Cleaning and inspection techniques 39
4. REACTOR PHYSICS 41
Circulating-Fuel Aircraft Reactor ~A
41
Oscillations 42 Slow kinetic effects 44 Critical mass 44 Neutron leakage spectra 46
Alkali Hydroxide Moderated Aircraft Reactor
48
Survey Calculations of the Circulating-Fuel ARE
48
ARE core design 48 Critical mass and total uranium investment 50 Reactivity coefficients 50 Power distribution 51
Neutron flux and leakage spectra 52
Statics of ARE Controls 54
Shim control requirements 54 Regulator rod 54 Safety rods
55
Specific Design Problems of the Circulating-Fuel ARE
57
5. CRITICAL EXPERIMENTS
59
Direct-Cycle Reactor
59
I
Control rod calibration
59
Temperature effects
61
I
Reflector studies 61
1% -Graphite Reactor 62 Circulating-Fuel Reactor 62 Correlation of Theory and Critical Experiments
63
Criticality with nonhydrogenous moderators 63
Criticality with hydrogenous moderato
65
y]
Foil exposures 65 Danger coefficients 66 Rod sensitivity 66 Gap experiment
PART II. SHIELDING RESEARCH
69
i SUMMARY AND INTRODUCTION
71
6. BULK SHIELDING REACTOR 73.
Mockup of the Divided Shield
73
Reactor Calibration
68
76
7. DUCT TESTS 79
Theoretical Treatment of Duct Transmission 79
Measurement of Air-Filled Ducts in Water 80 Straight ducts 80 Ducts with bends 80 Comparison with theory
80
8. TOWER SHIELDING FACILITY 89 Tower Facility Design 89 Experimental Program
89
9. NUCLEAR MEASUREMENTS 93
Measurements with the 5-Mev Van de Graaff Accelerator
Total cross section of iron 93
Inelastic scattering levels in iron 93
Time-of-Flight Neutron Spectrometer
93
Back gr.ound'measurements
93
Indium'resonances
IS.
94
93
PART III. MATERIALS RESEARCH 95 SUMMARY AND INTRODUCTION 97 10. CHEMISTRY OF HIGHTEMPERATURE LIQUIDS
99
Low-Melting-Fluoride Fuel Systems
99
NaF-BeF2-UF4 100 KF-BeF2-UF4 101 RbF-BeF2-UF4 101 LiF-NaF-BeF2-UF4 101
Fuel containing zirconium fluoride 101
Simulated Fuel Mixture for Cold Critical Experiment 102
Ionic Species in Fused Fluorides 102
Preparation of Standard Fuel Samples 103 Preparation of Pure Hydroxides 104 Coolant Development
104
LiF-ZrF4 105 NaF-ZrF4 105 KF-ZrF4 105 RbF-ZrF4 105 NaF-KF-ZrF4 105 NaF-RbF-ZrF4 105 NaF-KF-LiF-ZrF4
106
Preparation of Pure Fluorides
106
Fuel preparation equipment
106
Fuel handling equipment 107
11. CORROSION RESEARCH
109
Static Corrosion by Fluorides
,~,
110
Effect of pretreatment of fuel 110 Corrosion of structural metals 110 Corrosion by fluorides with various additives
112 Melting point-of fluorides after corrosion tests 113
Static Corrosion by Sodium Hydroxide
114
Corrosion of special alloys 114 Corrosion by sodium hydroxide with various additives 115 Corrosion of refractory
materials
116
Static Corrosion by Liquid Metals 116
Corrosion by low melting point alloys
116
Corrosion by sodium-lead alloy
118
Facilities for Dynamic Corrosion Testing
119
Thermal convection loops, 119 Seesaw corrosion tests 120 Differential temperature tests 120 Rotating dynamic
corrosion tests 120 Forced convection loops 122
Dynamic Corrosion by Fluorides 122
Corrosion by fluorides in thermal convection loops 122 Corrosion by fluorides in a seesaw furnace 124 Standpipe
tests of fluoride corrosion 124
Dynamic Corrosion by Hydroxides 127
Corrosion by hydroxides in thermal convection loops 127 Corrosion by sodium hydroxide in seesaw tests 129
Standpipe tests of sodium hydroxide corrosion
129
Fundamental Corrosion Research 129
Possible,equilibria among `fluorides and' metals
132
EMF measurements in fused fluorides 135 Electrode potentials in fused sodium hydroxide 135 Polarography of
sodium hydroxide in silver and platinum 136 Magnetic susceptibility of stainless steel exposed to fluorides 136
12. METALLURGY AND CERAMICS
139
Fabrication of Reactor Elements 139
Cold drawing of tubular solid fuel elements „
14
ARE control rod 140
Cone-Arc Welding
142
Equipment 142 Principle of operation 142 Experimental procedure
142
Brazing 143
Flow tests
144
Corrosion of brazing alloys
144
Mechanical Testing of Materials 147
Inconel creep and stress data 147 Tube-burst tests 148 Operation of creep and stress-rupture equipment
148
Ceramics Laboratory
151
Ceramic applications to reactors 151 Coatings for the radiator 151 Ceramic laboratory equipment 152 Microscopic
examination of fluorides 152
13. HEAT TRANSFER AND PHYSICAL PROPERTIES RESEARCH 153
Viscosity of Fluoride M fires
153
Viscosity of NaF-KF-LiF 153 Viscosity of NaF-KF-LiF-UF4 154 Modifications of viscosity apparatus
154
Thermal Conductivity of Liquids and Solids, 154 Heat Capacities 155 Vapor Pressure of Liquid Fuels 155 Physical
Property Data 156 Natural Convection in Confined Spaces with Internal Heat Generation 156 Analysis of Heat
Transfer in a Circulating-Fuel System 159 Heat Transfer Coefficients 161
Heat transfer in molten lithium 161 Heat transfer to fused salts and hydroxides 161 Entrance region heat transfer in a
sodium system 161
Heat Transfer of Boiling Liquid Metals
162
14. RADIATION DAMAGE
163
Irradiation of Fused Materials
163
Pile irradiation of fuel
164
Cyclotron irradiation of fuel
165
Inpile Circulating Loops 165 Creep Under Irradiation 165 Radiation Effects on Thermal Conductivity
166
j
PART IV. APPENDIXES 167 SUMMARY AND INIt QDUCT.ION 169 y' 15. THE' SUPERCRITICAL'-WATER
REAC` 171
Description of Reactor 171 Conclusion of the NDA Study 171 Recommendations of the NDA Study
172
16. ANALYTICAL CHEMISTRY 175 Studies of Diatomaceous Earth 175 Analytical Studies of Fluoride Eutectics
175
Uranium 176
Beryllium
176
Total alkali metals
176
Total fluoride 176 Nickel 177 Chromium 177 Manganese 177 Silicon 177
Solubility of Boric Acid -in Watei 177 Clarity .,Of' Borate.d Water" 177' Studies of Alkali and Alkaline Earth
Hydroxide Coolants 178 Analytical Services 178
17. LIST OF REPORTS ISSUED 179
18. DIRECTORY OF ACTIVE ANP RESEARCH PROJECTS AT ORNL 183 Reactor and Component Design 183
Shielding Research 185 Materials Research 186 Technical Administration
r,
191
ORNL-1294
AIRCRAFT NUCLEAR PROPULSION PROJECT
QUARTERLY PROGRESS REPORT
for Period Ending June 10, 1952
FOREWORD
1
PART I REACTOR THEORY AND DESIGN 3 SUMMARY AND INTRODUCTION 5 1. CIRCULATING-FUEL
AIRCRAFT REACTORS 6
Reflector-Moderated Circulating-Fuel Reactor
6
Spherical Heat Exchanger and Shield Design
7
2. CIRCULATING-FUEL AIRCRAFT REACTOR EXPERIMENT
Core and Pressure Shell 9
Stress analysis of the pressure shell 9
Fluid Circuit
10
Control 12
Operation
12
Pretesting 12 Critical loading 12 Power operation
13
Shutdown
13
Building 13 Electrical power 13 Shielding by concrete pits'
13
3. EXPERIMENTAL REACTOR ENGINEERING 15
Seals and Closures
16
Seal tester 16 Stuffing-box seals 16 Bellows tests 17 Oval-ring seal
9
17
Pumps 17
ARE centrifugal pump 17 Laboratory-size maintained-level gas-sealed pump 17 Worthite frozen-sodium-sealed
pump 18 Durco convection-cooled frozen-sodium-sealed pump 18 Durco frozen-fluoride-sealed pump 18 Fluoride
pumps with stuffing-box seals
19
Valves 19
Wide-open valve 20 Closed valve 20 Throttling valve 20 Canned-rotor-driven valve
20
Heat Exchangers 20
NaK-to-NaK heat exchanger 22 Tube-matrix spacer tests 22 Sodium-to-air radiator 24 Fluoride-to-liquid-metal heat
transfer system 26
Instrumentation 26
Pressure measurement
26
Liquid-level indicators
26
Fluid Dynamics of the ARE
28
Technology of Fluoride Handling 29
Fluoride production 29 Fluoride removal 29 Pretreatment of pipeline helium 29 Pickling procedures for fluoride
containers
30
4, REACTOR PHYSICS 31 Oscillations in the Circulating-Fuel Aircraft Reactor 31 Calculations for the
Circulating-Fuel ARE 32 Methods for Reactor Computation 33
5. CRITICAL EXPERIMENTS
Direct-Cycle Reactor
34
Shelf-type reactor assembly
Box-type reactor assembly;
Circulating-Fuel Reactor 38
Reactor materials 38
Reactor assembly 38
34
34
36
Graphite Reactor 39
Critical mass 39 Control rod calibration 39 Gap effect 39 Flux and power distribution 39 Danger coefficient
measurements 40
PART II SHIELDING RESEARCH 41 SUMMARY AND INTRODUCTION 43 6. BULK SHIELDING
REACTOR
43
Mockup of the Divided Shield'
44
Air-Scattering Experiments
47
Shield arrangement 47 Radiation dosage at crew compartment 47 Attenuation of gamma rays by lead 49
Comparison of experiment with standard design conditions
49
Determination of the Albedo of Neutrons and Gamma Rays 52 Irradiation of Animals 54 Irradiation of Electronic
Equipment
54
7. GAMMA-RAY ATTENUATION EXPERIMENTS IN THE LID TANK
63% Iron-37% Water Thermal Shield
54
54
63% Iron-37% Borated Water Thermal Shield 55 Solid Iron Thermal Shield in Water 55 Solid Lead Shadow Shields
in Water 55
8. DUCT TESTS 69
Duct Tests in the Thermal Column 69
Straight ducts 6 9 Ducts with bends 71 Wall-scattering experiment 71 Comparison with theory
72
GE-ANP Annular Air Ducts
72
9. NUCLEAR MEASUREMENTS 76
Cross-Section Measurements with Van de Graaff Accelerator 76
Time-of-Flight Neutron Spectrometer
76
PART III MATERIALS RESEARCH
79
SUMMARY AND INTRODUCTION
81
10. CHEMISTRY OF HIGH-TEMPERATURE LIQUIDS
82
Low-Melting-Point Fluoride Fuel Systems 83
NaF-KF-ZrF4-UF4 83 KF-ZrF4 -UF4 85 NaF-ZrF4 -UF4 85 NaF-RbF-ZrF4-UF4
85
Analyses of Fluoride Compounds 85
X-ray examination of solid, complex fluorides 85 Spectrographic analysis 86 Study of solid phases in the NaFBeF2-UF4 system 86 Petrographic examination of fluorides 88
Simulated Fuel Mixture for Cold Critical Experiment 89
Preparation of Pure Hydroxides
89
Sodium hydroxide
90
Lithium hydroxide
90
Potassium hydroxide
90
Coolant Development 90 NaF-ZrF4 91 KF-ZrF4 91 RbF-ZrF4 92
NaF-KF-ZrF4 92 NaF-RbF-ZrF4 93 NaF-ZnF2 94 KF-ZnF2 94 RbF'-ZnF2 96 NaF-KF-ZnF2
Fuel Preparation and Liquid Handling
96
Zirconium fluoride production
97
Preparation of pure fuel mixtures 97
Liquid handling equipment
99
Solubility of Uranium in Sodium Cyanide 99
96
11. CORROSION RESEARCH
100
Static Corrosion by Fluorides
101
Effect of additives 101 Temperature dependence 103 Effect of plating metals 103 Effect of cold-work
Corrosion of ceramic materials
104
Static Corrosion by Hydroxides
105
Effect of additives
105
104
Effect of plating metals
105
Dynamic Corrosion by Liquid Metals
107
Dynamic Corrosion by Fluorides 107
Corrosion by fluorides in seesaw tests 107 Corrosion by fluorides in thermal convection loops 109 Corrosion in
rotating dynamic test rig 116
Dynamic Corrosion by Hydroxides 116
Corrosion by hydroxides in seesaw tests 116 Standpipe tests of hydroxide corrosion 118 Hydroxide corrosion in
cold-finger thermal convection
apparatus
118
Modified thermal convection apparatus - TCA
118
Fundamental Corrosion Research 119
Interaction of fluorides and structural metals 119 Synthesis of complex fluorides 120 Examination of corrosion
products 121 X-ray-diffraction studies 123 EMF measurements in fused fluorides 124 Reactions in fused sodium
hydroxide 124 Compounds resulting from hydroxide corrosion 125 Mechanism of fluoride corrosion 126 Freeenergy relations of fluorides and structural metals 128 Solution of metals in molten halides 128 Fluoride corrosion
phenomena
129
12. METALLURGY AND CERAMICS
131
Loose Powder Bonding 131
Sintering temperature 132 Sintering time 132 Fuel-component particle size 132 Surface preparation 135 Sintering
under load
135
Control Rod Fabrication 135
Safety rod slugs 135
Regulating rod slugs
135
Mechanical Testing of Materials 136
Stress-rupture tests in argon
136
Stress-corrosion tests
136
Cone-Arc Welding
138
Effect of welding conditions
138
Heat exchanger assembly 139
Tests of Brazing Alloys 140
Nicrobraz 140 Manganese-nickel 140 Palladium-nickel 143 Ni-Cr-Si-Mn alloys 143 Silver-base alloys
Ceramics
144
Ceramic coatings for metals
144
Ceramics laboratory program
146
143
13. HEAT TRANSFER AND PHYSICAL PROPERTIES RESEARCH 146
Viscosity of Fluoride Mixtures
146
BeF3-bearing fluorides 147 ZrF4-bearing, fluorides 147 Material from corrosion loops 148 NaF-KF-LiF and NaFKF-LiF-UF4 mixtures
148
Thermal Conductivity 149 Heat Capacity 149 Density 150 Vapor Pressure of Fluorides 150
Beryllium fluoride
150
ZrF4-bearing fluoride mixtures
150
Physical Property Data
152
Heat Transfer in Sodium Hydroxide
152
Boiling Heat Transfer
156
Entrance Region Heat Transfer
156
Natural Convection in Confined Spaces with Internal Heat
Generation
158
Circulating-Fuel Heat Transfer Studies
159
14. RADIATION DAMAGE
Irradiation of Fused Materials
Pile irradiation of fuel
160
159
160
Cyclotron irradiation of fuel
163
Inpile Circulating Loops 163 Creep Under Irradiation 164 Radiation Effects on Thermal Conductivity
PART IV APPENDIXES 167
SUMMARY AND INTRODUCTION
164
169
15, ANALYTICAL CHEMISTRY 170
Analyses for Components of Fluoride Mixtures
170
Total alkali metals 170 Sodium, potassium, and lithium 170 Beryllium 170 Zirconium
Analyses for Impurities in Fluoride Mixtures 171
Iron
171
Chromium
171
Analyses for Impurities in Fluoride Compounds
171
Sulfate and sulfide 171 Zirconium oxide and oxyfluoride 172 Water
172
170
Service Analysis 172
16. LIST OF REPORTS ISSUED 173
17. DIRECTORY OF ACTIVE ANP RESEARCH PROJECTS 176 Reactor and Component Design 176 Shielding
Research 178 Materials Research 179
Technical Administration of'Aircraft Nuclear Propulsion
Project at Oak Ridge National Laboratory 184
ORNL-1375
AIRCRAFT NUCLEAR PROPULSION PROJECT
QUARTERLY PROGRESS REPORT
for Period Ending September 10, 1952
FOREWORD , !
!I
!
~
PART I. REACTOR THEORY AND DESIGN
3
SUMMARY AND INTRODUCTION
5
/
~
l. CIRCULATING-FUEL AIRCRAFT -.--- EXPERIMENT
~
-- Fluid Circuit ' 6
Pressure-Shell Stress Analysis
7
~
Reflector Coolant
| 11
Instrumentation /
12
Off-Gas System . ~
~ , , . , . . 12
Reactor Control System ^ . . .~ . . . . ^ . ! 12
Shielding
~
/ 13
2. EXPERIMENTAL REACTOR ENGINEERING , 13
Pumps 15
Frozen-sodium-sealed pump in figure 8 loop
15
Durco frozen-fluoride-scaled pump
15
Laboratory-size muintninr6-ll vv} gas-sealed pump . ^
Durco pump with shaft packing
17
|
ARE centrifugal pump
` 17
Valves ~
19
Bellows type of valve-stem seal
~lg
High-tnmpezxt"r, valve-stem »vckings
|lg
Self-welding of seat materials
20
~
Canned-rotor-driven valve .~
~
20
Heat Exchangers `
' 20
Test of core element of sodium-to-air radiator
~
Bifluid heat transfer loop 21
'
NaX-t"-NaD heat exchanger
23
/
Instrumentation 23
Rotameter type of f1n°metrc ~
23
Rotating-vane type of flowmeter 24
Moore uullmativ!prousnro-mo^oxriug device
~
Diaphragm pressure-measuring device
Diaphragm pressure transmitters 25
Moving-probe level indicator
°
26
~
Null-balance level control . ',
26
~
Strain-gage level indicator ~
|26
Fluid Dynamics 26 ~
~
ARE core mockup ,
26
20
Possible fuel-header manifold for the reactor core
Technology of Fluoride Handling 29
29
~
25
' 16
25
6
Fluoride production
29
Removal of fluorides from contaminated systems
30
Purity of pipe line helium 31
Fluoride plug-removal test from simulated ARE core 31
Injection of NaK into a flowing fluoride stream
31
Gas-line-plugging tests
32 Cooled-baffle vapor trap for zirconium-bearing fluoride fuel . . . 34
Descaling and pickling tests
34
3. REACTOR PHYSICS 3 5
Oscillations in the Circulating-fuel Aircraft Reactor 36
Effect of Gaps on Reactivity
38
Slowing-Down Kernels 40
4. CRITICAL EXPERIMENTS
Direct-cycle Reactor
40
Reflector studies 41
Poison rod calibrations
42
ARE Critical Assembly 43
40
PART II. SHIELDING RESEARCH
SUMMARY AND INTRODUCTION
5. LID TANK EXPERIMENTS
48
Air Ducts
48
R-1 Reactor Gamma Shielding
53
Other Lid Tank Experiments
56
Correlation of Neutron Attenuation Data
45
47
6. BULK SHIELDING REACTOR
Mockup of the Divided Shield
64
Air-scattering Experiments
64
Reactor Power Determination
64
Irradiation of Animals
66
Irradiation of Electronic Equipment
Capture Gamma-Ray Measurements
7. TOWER SHIELDING FACILITY
63
63
69
70
70
8. NUCLEAR MEASUREMENTS 71
Fission Cross Section of U234 and U235
71
~
Total Cross Section of N14
!
Time-of-Flight Spectrometer ^ ^!
PART 111. MATERIALS RESEARCH
^ ^ .. .^ .. .
71
! ^ ^ . . . ^ . .^ , .. 72
^,..
73
'
SUMMARY AND INTRODUCTION
75
~ 9. CHEMISTRY ' OF HIGH-TEMPERATURE LIQUIDS ^ ^ , , , , , , , ^ , , , ^ ^ , .
~
Fuel Mixtures Containing DP* . ~ !,
77
NaF-KF-ZzF ^'UF « ~
|~ ^ ,
~
0a -%rF+-DF* ~ 78
~
Nup-Zry«-DoF u-UF
/
%n
-UP* . . . ^ ,
^ . . . ^ , 77
~,
~^ . .
'^
~ 78
^...~ ^..
Fuel Mixtures Containing UF s
NaF-KF-LiF-UF3
'
~
BP°UF ~
~ 81
79
'^
' 79
.
79
76
NaF-UF3
81
Preparation of compounds of 0F 3 81
Alkali Fluoborate Systems
~ 82
Vapor pressures of commercial flno6orut~~ 82
Thermal data for flnn6orote systems
82
Differential Thermal Analysis ^
84
'
X-Ray Studies of Complex Fluoride Systems
Nm a %zy z-Nau Up-/ , '
/ 85
~
NouZrF~-Ma,0P ~
86
N«%rFs-NaUF» ^ ^ ` ^ . . ^ . ^ ~ , . . . ^
86
Spectrographic Analysis of Fluorides
...^
^ . . . , ~ 87
~
Simulated Fuel Mixture for Cold Critical Experiment 87
Moderator Coolant Development
Coolant Development , , . . . ,!
/,
DbF-A1y» ,
89
NaF-KF-AIF3 . ^
89
^
~
88 !
89
N»F-%r -&lF y ~ 89
~
NaF-ZrF4
~
~ 89
%c +-Bo e
^~. ^
90
.
Hydrolysis and Oxidation of Fuel ~~~tvre^ ! 90
/
Heat of solution and heat of formation of uranyl fluoride . . . . 90
Free energy change for the reaction of uranium tetrafluoride
!
with oxygen . . . . ^
~,
90
Fuel Purification Research
PI
Purification of molten fluorides
91
Preparation of pure zirconium tetra{loorid~ 92
Preparation of pure aluminum fluoride
93
Reaction of Fuels with Alkali Metals
Service Functions
94
93
CORROSION RESEARCH
95
Parametric Studies of Fluoride Corrosion
96
Temperature of test
96
Length of test
96
Residual stresses in specimen
99
Carbon content of specimen
99
Corrosion inhibitors
100
Pretreatment
101
Seesaw and Static Tests with Fluorides Containing ZrF4
103
Fluoride Corrosion in Thermal Convection Loops
103
Fluoride mixtures containing ZrF4 104
Effect of cleaning loops 104
Corrosion inhibitors
108
Crevice corrosion
109
Temperature variations
110
Variations in alloy composition of the walls 110
Postrun examination of fuels
112
Compatibility of Beryllium Oxide with Various Fluoride Mixtures . . . 112
85 ~
Hydroxide Corrosion
114
Temperature of test
114
Residual stresses in specimen
114
Corrosion inhibitors
115
Hydrogen atmosphere
115
Liquid Metal Corrosion 117
Mass transfer in liquid lead
117
Effect of temperature on lead corrosion
118
Lead-sodium mixtures
118
Spinner tests with sodium 119
Type 1020 chromized steel in low-melting-point alloys
NaK, and lead . . . . 119
Fundamental Corrosion Research 121
Interaction of fluorides with structural metals
121
Synthesis of complex fluorides
122
EMF measurements in fused fluorides
123
Polarographic studies in sodium hydroxide 124
Electrochemistry of sodium hydroxide
124
Mechanism of fluoride corrosion 126
Tripositive nickel compounds from hydroxide corrosion
Solutions of metals in molten halides
130
Fluoride corrosion phenomena
130
119 Compatibility of beryllium oxide with sodium,
127
11. METALLURGY AND CERAMICS
131
Control Rod Fabrication 131
Mechanical Testang of Materials • 132
Physical testing in fluorides
132
Creep and stress-rupture tests in argon
133
Welding
133
Cone-arc welding
135
Specifications for ARE welding
135
Tests of Brazing Alloys 138
Static corrosion tests of brazed joints
138
Tensile strength of brazed joints
138
Brazing of molybdenum 140
Dry-hydrogen brazing furnace
140
Reduction of Molybdenum Disulfide
• . . . . . 141
Ceramics Research • . . . . . . . . . . . . . . . . . . . . . . . . 143 Ceramic coatings for metals
Ceramic reflector
143
143
12. HEAT TRANSFER AND PHYSICAL PROPERTIES RESEARCH
144
Viscosity of Fuel Mixtures
145
NaF-ZrF4-UF4 fuels
145
Capillary viscometer
145
Thermal Conductivity of Liquids; 146
Heat Capacity
146
Density 147
Vapor Pressure of Fuel Constituents
147
Zirconium tetrafluoride • . . . . . . . . . . . . . . . . . . 147
Zirconium-bearing fluoride mixtures
147
Convective Heat Transfer in Molten Sodium Hydroxide
148
Boiling Heat Transfer in Mercury 149 Natural Convection in Confined Spaces with Volume Heat Generation . .
149 Heat and Momentum Transfer Analysis of the Thermal Convection Loops . . 152
13. RADIATION DAMAGE
Irradiation of Fused Materials
•............ ....
• . . . . . 153
. . . . . . 152
In-Reactor Circulating Loops
154
Creep, Under Irradiation • . . . . . . . . . . . . . . . . 154
Radiation Effects on Thermal Conductivity • . . . . . 156
PART IV. APPENDIXES 157
SUMMARY AND INTRODUCTION
159
14. ANALYTICAL CHEMISTRY 159
Analytical Studies of Components of Fluoride Mixtures
159
Alkali metals
159
Zirconium
160
Analytical Studies of Impurities in Fluoride Mixtures 160
Chromium
160
Nickel 161
Oxygen 161
Chloride
161
Water 162
Determination of Carbon in ZrF4 and ZrO2-NaF-C Mixtures 162
Compatibility of Reactor Fuels and NaK
162
Service Analysis 163
15. LIST OF REPORTS ISSUED 164
ORNL-1439
AIRCRAFT NUCLEAR PROPULSION PROJECT
QUARTERLY PROGRESS REPORT
for Period Ending December 10, 1952
FOREWORD
i
PART I. REACTOR THEORY AND DESIGN
SUMMARY AND INTRODUCTION
5
1. CIRCULATING-FUEL AIRCRAFT REACTOR EXPERIMENT
7
Fluid Circuit
7
Stress Analysis of Piping 8
Reactor 11
Instrumentation 11
Off-gas System 11
Description of the system 11
Maximum activity of stack gases 12
Normal discharge from the surge tank
15
Gas vented from the fuel dump tank during dumping 15
Reactor Control System 15
2. EXPERIMENTAL REACTOR ENGINEERING 17
Pumps for High-Temperature Fluids
17
Pump with combination packed and frozen seal
17
Pump with frozen-sodium seal
19
Allis-•Chalmers pump
19
Laboratory-sized pump with gas seal
19
ARE pump
21
Rotating Shaft and Valve Stem Seal Development
21 Screening tests for packing materials and
lubricants . . . 21
Packing compression tests
23
Packing penetration tests 23
Face seal tests 25
Combination packed and frozen seal
25
Frozen-lead seal 26
Frozen-sodium seal
26
Bellows-type of valve stem seal
26
Heat Exchangers 27
Sodium-to-air radiator
27
Bifluid heat transfer system
28
Instrumentation 29
Botameter type of flowmeter
29
Rotating-vane flowmeter 30
Diaphragm pressure-measurement device 30
Moore Nullmatic pressure transmitter
Handling of Fluorides and Liquid Metals
NaK distillation test
32
Gas-line plugging
32
ZrF4 vapor condensation test
32
Project Facilities 33
Helium distribution
33
Fabrication shop 33
Instrument shop facility 33
30
32
Gas-fired furnace facility 33
3. GENERAL DESIGN STUDIES 35
Air Radiator Program
35
Radiator Performance
35
Engine Performance
35
Heat Exchanger Design Charts
40
4. REACTOR PHYSICS 41
Oscillations in the Circulating Fuel Reactor 41
Limits on the oscillations 42
Periodic oscillations
42
Specific examples
44
Reactor Calculations
44 Temperature Dependence of a Cross Section Exhibiting
a Resonance
46
5. CRITICAL EXPERIMENTS
48
Reflector-Moderated Circulating-Fuel Reactor Assembly
48
ARE Critical Assembly 52
PART II. SHIELDING RESEARCH
SUMMARY AND INTRODUCTION
61
6. DUCT TESTS IN LID TANK FACILITY
62
G-E Outlet Air Duct
62
Neutron dose measurements
62
Calculated neutron dose 62
G-E Inlet Air Duct
71
Induced Activity Around a Duct 74
Radiation Around an Array of Cylindrical Ducts
76
7. BULK SHIELDING FACILITY 85
Measurements with the Divided-Shield Mockup
85
Air-Scattering Experiments
~, . . . . 86
Irradiation of Animals
85
Other Experiments
92
8. TOVER SHIELDING FACILITY ,
^,
95
_
Facility yDesign . ^ . , , ^ . ^ , ^ . ^ , , ,
^ ^ . , ^ ~96
Structure Scattering ,
^,
95
9. NUCLEAR MEASUREMENTS ^
96
Angular Distribution of Neutrons Scattered fr~um Nitrogen . . . . 96 Results of nitrogen-scattering experiment
96
Analysis of nitrogen-scattering data
'
6
A Fast-Neutron Base Measurement '97
PART III. MATERIALS RESEARCH
/
SUMMARY AND INTRODUCTION
^,
103 '
10. CHEMISTRY OF HIGH-TEMPERATURE LIQUIDS . . . '
105
Fuel Mixtures Containing OF. ~
105
LiP-BoF m -'
.,^
~^
^^~'...^^
105
/
Nup-8rF 2
105
[iF-Zr -QP
,..^^^~..^.,.^^,..^^
107
NaF-LiF-DF.
,.^,
^
^~ ~ . . . ,
107
Nu%rP -NuOP l07
~,
,
.
^
.
,
.
./ .
.
^
.
^
.
^
R6y-&]F»-0P° ^
107
Fuel Mixtures Containing OCl^ . . ^ ~
108
Fuel Mixtures Containing UF3 ,
^
109
NaF-DFa
109
KF-UF3
^
llU
Alkali Fluoborate Systems . ^
~
110
Differential Thermal Analysis , . ^ ,
ill
Simulated Fuel for Cold Critical Experiment
112
Coolant Development
\l2
NaF-ZrF4
~
112
LiP Z^ ^
^
'
'
^
^
^
^
^
^
`
^
^
^
.
113
Nap-KF-AlFs , , , , , ^ , _ ^ , , , , , ^ , . ^ ,
113
NmF-8eF z _ + , . . ^ . . ^ 114
NaF-LiF-ZrF4 , ^ , ^ ~ ^ , _ , _ _ . ^ ~ . . , ^ . ^ ^ . ^ ^ ^
114
NaF-BaF2
.,
,
^
,,^
_,,^^,,^,^
NaF-KF-LiF-ZrF4
~..^..^^..^~.,..^.,
115
NmF-B6P-AlP . .
115
*
..,^....~.^..^.
.
.^
Studies of Complex Fluoride Phases
^
115
K3 CrF6 -Na3 CrF6 -Li CrF
115
Solid phases in NaF-BeF2-UF4 and NaF-ZrF4 systems
UF3 -ZrF4
115
NaF-ZrF4
118
Other fluoride complexes 118
Reaction of Fluoride Mixtures with Reducing Agents 118
Reducing power of various additives
118
Identification of reduction products
119
Reaction of fluoride mixtures with NaK
120
Reaction of NaF-ZrF4-UF4 with ZrH2
120
Solubility of potassium in NaF-KF-LiF eutectic
121
Production and Purification of Fluoride Mixtures
122
Laboratory-scale fuel preparation 122
Pilot-scale fuel purification
122
Fuel production facility 123
Preparation of hydrofluorinated fuel samples
124
Hydrofluorination of Zr02-NaF mixtures
124
Purification of Hydroxides
125
11. CORROSION RESEARCH
127
Fluoride Corrosion in Static and Seesaw Tests
Oxide additives 127
Comparison of liquid- and vapor-phase corrosion
Crevice corrosion
128
Carboloy and Stellite alloys
130
Reducing agents 130
Fluoride treatment
131
Temperature dependence 132
Ceramic materials
132
Fluoride Corrosion in Thermal Convection Loops
Mixtures containing ZrF4 133
Hydrofluorinated NaF-KF-LiF-UF4
136
Corrosion inhibitors
137
Inserted corrosion samples
138
Crevice corrosion
138
Variation in loop wall composition 139
127
127
133
115
`'
`
^
`
`
.
'
.
,,,
.,,
.^.~
115
^
.
Self-insulating properties of fluorides
Other loop tests 139
Hydroxide Corrosion
141
Corrosion inhibitors
141
Temperature dependence 141
Nickel alloys in NaOH
141
139
Compatibility of BeO in KOH
141
Nickel in NaOH under hydrogen atmosphere 142
Liquid Metal Corrosion • . . . . . . . . . . 144
High-velocity corrosion by sodium • . . . . . . . . . . . 144
Ceramic materials in sodium
• . . . . . . . . . . . 146
Lead in metal convection loops
147
Lead in quartz convection loops
148
Compatibility of BeO in NaK
150
Sodium in forced-convectionloops 150
Fundamental Corrosion Research 151
Interaction of fluorides with structural metals
152
Air oxidation of fuel mixtures
152
EMF measurements in fused fluorides
153
Preparation of trivalent nickel compounds in the hydroxides . . 154
12. METALLURGY AND CERAMICS
• . . . . . . . . . . . 155
Fabrication of Solid Fuel in Spheres
155
Suspension in refractory powder 1.56
Momentary melting in a high-temperature arc
156
Spraying from a metallizing gun 156
Solid Phase Bonding of Metals
156
Columbium Research
157
Gaseous reactions
157
Oxidation in air 158
Creep Rupture Tests of Structural Metals
159
Inconel in air
159
Inconel in hydrogen
159
Inconel in molten fluorides'
159
Type 316 stainless steel in argon 159
Type 316 stainless steel in molten fluorides 159
Brazing and Welding Research
161
ARE welding
161
Cone-arc welding
161
Resistance welding
162
Automatic heliarc machine welding
164
Fabrication of heat exchanger units 164
Brazing of copper to inconel
165
Evaluation Tests of Brazing Alloys 165
Oxidation of brazing alloys'
165
Corrosion of brazing alloys by sodium hydroxide
168
Corrosion of brazing alloys by sodium and lithium 168
Tensile strength of brazed joints
169
Melting point of 60% Pd-40% Ni alloy
171
Ceramics Research
171
Development of cermets for reactor components
Ceramic coatings for an aircraft-type radiator
Ceramic coatings for shielding metals
171
Uniformity of beryllium oxide blocks
171
171
171
13. HEAT TRANSFER AND PHYSICAL PROPERTIES RESEARCH
174
Thermal Conductivity of Liquids 174
Heat Capacity of Liquids 176
Viscosities of Fluoride Mixtures 176
Measurements with the Brookfield viscometer
176
Capillary viscometer
176
Density of Fluoride Mixtures
178
Vapor Pressure of Molten Fluorides
178
Convective Heat Transfer in Fluoride Mixture NaF-KF-LiF 179
Analysis of Specific Reactor Heat Transfer Problems 180
Heat Generation in the reactor reflector
180
Analysis of fluid-to-air radiators 181 Natural Convection in Confined Spaces and Thermal Loop Systems . 182
Turbulent Convection in Annuli
182
Circulating-Fuel Heat Transfer
185
14. RADIATION DAMAGE
186
Irradiation of Fused Materials
186
In-Reactor Circulating Loops
187
Creep Under Irradiation 188
15. ANALYTICAL STUDIES OF REACTOR MATERIALS 190
Chemical Analysis of Reactor Fuels
190
Zirconium
191
Chromium
192
Aluminum
192
Oxygen 192
Water 192
Determination of Beryllium in NaK
192
Spectrographic Analysis 193
Uranium oxides 193
Nickel fluoride 193
Petrographic Examination of Fluorides
193
ZrO2 HF
193
NaF-ZrOF2
193
Optical Properties of Some Fluoride Compounds
194
Na2UF6
194
K3UF7 194
Na3ZrF2
194
2 ZrF4 . UF3
194
Chemical Analyses for U02 in UF3
194
Service Chemical', Analyses
194
PART IV. APPENDIXES'
SUMMARY AND INTRODUCTION
199
16. LIST OF REPORTS ISSUED 199
17. DIRECTORY OF ACTIVE ANP RESEARCH PROJECTS AT ORNL
202
1. Reactor and Component Design 202
II. Shielding Research
203
III. Materials Research
204 IV. Technical Administration of Aircraft Nuclear
Propulsion Project at Oak Ridge National Laboratory . . .
209
ORNL-1515
AIRCRAFT NUCLEAR PROPULSION PROJECT
QUARTERLY PROGRESS REPORT
for Period Ending March 10, 1953
FOREWORD
1
PART I. REACTOR THEORY AND DESIGN
INTRODUCTION AND SUMMARY
11
5
1. CIRCULATING-FUEL AIRCRAFT REACTOR EXPERIMENT
.
.
7
Fluid Circuit
7
Stress Analysis •
7
Reactor 11
Instrumentation 11
Off-Gas System 11
Reactor Control • . . .
11
Electrical System
15
2. EXPERIMENTAL REACTOR ENGINEERING 17
Pumps for High-Temperature Liquids
18 Centrifugal pump with, combination packed and frozen
seal
for fluorides
•
18 Allis-Chalmers centrifugal pump for liquid metals . . . . 18
Laboratory-size pump with gas seal
18
ARE-size sump pump
20
ARE centrifugal pump
21
Electromagnetic pump
22
Rotating-Shaft and Valve-Stem-Seal Development 22
Mechanical face seals
22
Combination packed and frozen seal with MoS2
25
Combination packed and frozen seal with graphite 26
Graphite packed seal
26
Rotating-shaft seal test
28
Packing penetration tests a
28
Frozen-sodium and frozen-lead seal for NaK
29
ARE valve test 29
Heat Exchanger Systems • . . . . 30
Sodium-to-air radiator tests
30
Bifluid heat transfer loop • . • . . . 30
ARE Fuel Circuit Mockup
•.•
31
Vortexes and bubbles
32
Operational instabilities 33
Instrumentation • • a
35
Pressure measurement I 35
ARE leak detection indic~r tests
36 l
Slip rings for temperature measurement
`. . • . . • . . . • • 36
Rotameter type of flowmeter
•.•
36
Handling of Fluorides and Liquid Met' ls,:' 36
Distillation of NaK
36
Flame tests for NaK vapor in helium
••
37
3. REACTOR PHYSICS •
39
4. REFLECTOR-MODERATED CIRCULATING-FUEL REACTOR 41
Static Physics
• • . • . 41
Reactors with various reflector-moderators • .
44
Reactors with beryllium'reflector-moderators
46
Summary tables and graphs
51
Critical Experiments
53
First critical assembly
•
53
Second critical assembly 56
Design Characteristics
•.
61
Factors affecting core diameter
•..•
64
Temperature, pressure, and stress 66
Reflector heating . .
•
•
•
••
69
<,
Shielding . . • . . . . •
•.
.•
74
Power Plant Design
79
PART II. SHIELDING RESEARCH
INTRODUCTION AND SUMMARY
••.•.••.•
87
5. LID TANK FACILITY . .
•
•...
89
Effective Fast-Neutron Removal Cross Sections
89
Mockup of the Unit Shield of the Reflector-Moderated Reactor . .
6. BULK SHIELDING FACILITY • • • • • . . . .
91
Air-Scattering Experiments • . •
• . . • . . 91
Irradiation of Animals . . . . • . •
91
Neutron Spectroscopy for the Divided Shield
92
Gamma Spectroscopy for the Divided Shield
92
Fission Energy and Power in the Bulk Shielding Reactor •
92
7. TOWER SHIELDING FACILITY
~7
Tower Design • •
• . • .. 7
Construction Schedule
• • . . • . • • . • • • •9
8. NUCLEAR MEASUREMENTS • • . • . • • • • • • . . 101
Fast-Neutron Scintillation Spectrometer • • . . . . • 101
Measurements with 6-Mev Van de Graaff • • . .
101
PART III. MATERIALS RESEARCH
INTRODUCTION AND SUMMARY
,
,,
9. CHEMISTRY OF HIGH-TEMPERATURE LIQUIDS
Fuel Mixtures Containing UF4
107
LiF-ZrF4-UF4 , 107
KF-LiF-BeF2-UF4 .
.
.
.
.
Fuel Mixtures Containing ThF4
107
Fuel Mixtures Containing UCl4
108
NaCl-UCl4
109
KCl-UCl4
109
Fuel Mixtures Containing UF3
109
Addition of Reducing Agents to ARE Fuel 110
Coolant Development
112
LiF-ZrF4
112
CsF-ZrF4
112
KF-LiF-ZrF4
112
RbF-LiF-ZrF4 112
KF-LiF-BeF2
113
Production and Purification of Fluoride Mixtures
113
Laboratory-scale fuel preparation 113
Pilot-scale fuel purification
114
Fluoride production facility
115
Hydrofluorination of Zr02-NaF mixtures
115
10, CORROSION RESEARCH
117
Fluoride Corrosion of Metals in Static, Seesaw, and
Rotating Tests 118
89
,,
107
,
.
107
105
Crevice corrosion
118
High-temperature pretreatment of Inconel 118 Effect of time of exposure of Inconel to fluoride
mixture with and without ZrH2 added
118
Structural' metal fluoride additives 119
Hydrogen fluoride additive
120
Fluoride corrosion in a rotating rig 121
-Static tests on Incoloy and Inconel in fluorides
121
Fluoride Corrosion of Metals in Thermal Convection Loops . . . . 121 Effect of fluoride batch size 121
Fluoride pretreatment
122
Hydride additives
123
Metal additives 123
Temperature dependence 123
Crevice corrosion
124
Inserted corrosion samples .'
124Effect of exposure time 124
Nonuranium bearing mixtures
124
Liquid Metal Corrosion of Structural Metals 125
Seesaw tests-of sodium-lead alloys 125
Static tests with lithium 126 Incoloy in sodium, lithium, and lead . . 126
Corrosion by lead in thermal convection loops . . .
128
Corrosion of Ceramics by Fluorides and Liquid Metals 129 Cermets in fluorides and liquid metals 129
Static tests of the ARE-BeO blocks in Na and NaK 131
Seesaw tests of BeO in NaK
132
Convection loop tests of BeO in NaK
132
Solubility of BeO in NaK 133
Effect of Atmosphere on the Mass Transfer of
Nickel in Hydroxides
136
Fundamental Corrosion Research
136 Identification of corrosion products from convection loops . . 136
Preparation of special complex fluorides
137
Air oxidation of fuel mixtures
137
11. METALLURGY AND CERAMICS
139
Welding and Brazing Research
140
Cone-arc welding
140
Fabrication of heat exchanger units 140
Brazing of copper to Inconel
142
Evaluation Tests of Brazing Alloys 143
Corrosion of brazing alloys by fluorides
143
Effect of brazing time on joint strength
143
Effect of spacing on brazed joint strength 144
Strength of brazed joints with various base metals
145
Creep-Rupture Tests of Structural Metals 145
Preoxidized Inconel in argon
145
Peened Inconel in argon 146
Effect of Inconel grain size on time to rupture
147 Effect of environment on strain vs. time curves for
Inconel . . 147
Type 316 stainless steel tube burst tests in argon
148
Fabrication of Control and Safety Rods
148
Control` rods for the G-E'R-1 Reactor
'148
Tower shielding facility safety rods
150
Columbium Research
:
Gaseous reactions
150
Oxidation
`'151
Fabrication of Metals . . . . .
152
High-conductivity metals for• radiator fins 152
Solid-phase bonding . . .c.t`~
152
Extrusion of high-purity tubing
152
Hot-Pressed Pump Seals • • • . . . 153
Ceramics
6
...
154
Ceramic coatings for shielding
154
Development of cermet fuel elements
154
Reduction of porosity of ARE beryllium oxide
155
12. HEAT TRANSFER AND PHYSICAL PROPERTIES
157
Thermal Conductivity of Liquids 157
Heat Capacity of Liquids 157
Viscosity and Density of Alkali Hydroxides 158
Vapor Pressures of Fluorides
159
Prandtl Moduli of Various Materials
160
Specific Reactor Heat Transfer Problems
160
Turbulent Convection in Annuli
160
Circulating-Fuel Heat Transfer
162
High Temperature Reactor Coolant'~Studies
163
13, RADIATION DAMAGE
165 Irradiation of Fused Materials . . . 165 In-Reactor Circulating
Loops
167
Creep Under Irradiation 167
14. ANALYTICAL STUDIES OF REACTOR MATERIALS 171
Chemical Analysis of Reactor Fuels and Contaminants
171
Zirconium
•
..
172
Reduction products
172
Oxides 173
Hydrogen fluoride
173
Corrosion products
175
Preparation of Uranium Tetrachloride
176
Petrographic Examination of Fluorides
176
UCl4 -NaCl system
176
UCl4-KCl system
176
X-Ray Diffraction Studies
177
Service Chemical Analyses
177
PART IV. APPENDIXES
15. LIST OF REPORTS ISSUED DURING THE QUARTER .
.
.
183
TECHNICAL ORGANIZATION CHART' OF" THE -ANP',PROJECT . ,
.
.
187
ORNL-1556
AIRCRAFT NUCLEAR PROPULSION PROJECT
QUARTERLY PROGRESS REPORT
for Period Ending June 10, 1953
FOREWORD ,
^.,,.^..^...,^.
I
PART L REACTOR THEORY AND DESIGN
INTRODUCTION AND SUMMARY
^
^,.,.,
5
1. CIRCULATING-FUEL AIRCRAFT REACTOR EXPERIMENT
6
Fluid Circuit
6
Reactor 6
'
Instrumentation 7
Off-GasSystem 7
Reactor Control 9
Electrical System
^
^.`.,^
^
9
Fuel Loading Facility
^
^,..,
9
Fire-Fighting P,eporutinna ,..,.^
^,,
^,^.^
9
2. EXPERIMENTAL REACTOR ENGINEERING 10
Pumps for High-Temperature Liquids
^^
^.^,... 10
Centrifugal pump with combination packed-frozen fluoride seal ...^,,,,.^ 10
ARE-size sump pump
^
^..`,,.
11
Frozen- uuJiun,soo!=6pvmp6x/\REnmJeroto,coo!ont circuit , ^,.^.^.. 11
ARE packed-frozen sealed fluoride pump , ^
^
15
Allis-Chalmers canned-rotor pump ^
15
Frozen-lead-sealed fluoride pump ^
15
Laboratory-size svmp-typ;pvmpwiH`gosxea! ,
^
^,,
^^,...
Rotating Shaft and Valve Stem Seal Development
17
Graphite-packed seals
17
Grooved-shaft packed-frozen seal tests
17
Bronze wool and MoS2 packed-frozen seal tests
^
18
Frozen-lead seal tests
19
V-ring omJ
^,
19
EeF seal tests o ` '^` `^ ' '^'^ ' ". ' ' ^' " . ' ' ' '^ ^' ^^^ " ^"^' ^" ,^"^^ ^ ^ 19
Packing penetration tests ,, ^
22
Instrumentation 22
Pressure measurement
22
NaK leak detection methods
23
3. REFLECTOR-MODERATED CIRCULATING- FUELREACTORS
Reactor Control ,, ^
^,...,
24
General Design Parameters ,
25
4. REACTOR PHYSICS 26
Kinetics of a Circulating-Fuel Reactor
26
Behavior at long time after a disturbance
26
Oscillations
26
The first overswing following a disturbance 27
Statics of the Circulating-Fuel ARE Critical Experiment
28
5. REFLECTOR-MODERATED REACTOR CRITICAL EXPERIMENTS
Power Distribution
30
Leakage Flux
31
Control Rod Measurements
31
17
24
30
Danger Coefficient Measurements 31
Correlation with Theory 31
PART II. MATERIALS RESEARCH
INTRODUCTION AND SUMMARY
37
6. CHEMISTRY OF HIGH-TEMPERATURE LIQUIDS
Fluoride Mixtures Containing UF4 39
NaF-ZrFAUF4 39
RbF-ZrF4- UF4 40
NaF-ZrF4 BeF2-UF4
40
Fluoride Mixtures Containing UF3 41
Chloride Mixtures Containing UCl4 „ - , , , 42
KCl-UCl4
42
LiCl-UCl4
42
TICl-UCl 4
42
KCl-Li Cl-UCl 4 42
Coolant Development
43
NaF-ZrF4BeF2 43
LiF-ZrF4
44
Differential Thermal Analysis
44
Production and Purification of Fluoride Mixtures
45
Removal of HF from fuel batches 45
Reduction of metal fluorides with H2
46
Pilot-scale fuel purification
47
Fluoride production facilities
48
Preparation of Complex Fluorides 48
X-ray Diffraction Studies 49
NaF-UF4
49
NaF-ZrF4
49
39
7. CORROSION RESEARCH
50
Fluoride Corrosion of lnconel in Static and Seesaw Tests
51
Effect of exposure time 51
Residual hydrogen fluoride
51
Fluoride pretreatment
52
Structural metal fluoride additions 53
Structural metal oxide additions
53
Chromium metal addition 54
Zirconium hydride addition
54
Carbon addition 55
Crevice corrosion
55
Inconel container pretreatment
55
Static Corrosion of Stellite by Fluorides
56
Fluoride Corrosion of Inconel in Rotating Test
57
Fluoride Corrosion in Inconel Thermal Convection Loops
58
Effect of exposure time 58
Temperature dependence 60
Chromium and nickel fluoride additives
60
Fuel purity
62
Loop oxide films 62
Nonuranium bearing fluorides
62
Fluoride Corrosion of Nickel, Thermal Convection Loops
62
Fluoride Corrosion of Type 316 Stainless Steel Thermal Convection Loops 64
Liquid Metal Corrosion 64
Mass transfer in liquid lead
64
BeO in sodium and NaK 68
Coated beryllium in sodium
Carboloy in lead and sodium
68
69
8. METALLURGY AND CERAMICS
71
Welding and Brazing Research
72
Welding of heat exchanger tube bundles
72
Brazing of air radiators
73
Dilution and diffusion of brazing alloys
73
Brazing Carboloy to stainless steel 74
High-temperature brazing alloy evaluation tests
76
Creep and Stress-Rupture Tests of Structural Metals 76
Fabrication Research
77 Extrusion of high-purity lnconel tubing ... 77
Air oxidation of columbium
77
Control rods for the G-E reactor
77
Hot-Pressed Pump Seals '79
Fabrication of small compacts with MoS2 79
Metallographic examination of compacts with MoS2 80
Fabrication of face seal rings
80
Surface sulfurization of molybdenum
80
High-Conductivity Metals for Radiators
81
Chromium-clad OFHC copper
82
Chromium and nickel electroplate on copper
82
Inconel cladding on copper
82
Type 310 stainless steel cladding on copper 82
Type 310 stainless steel cladding on silver 82
Copper alloys
82
Solid Fuel Formed in Spheres
83
Heating under vacuum
83
Three-phase carbon arc 84
Molten alloy passed through a small orifice 84
Settling of particles through a molten salt 84
Inflammability of Sodium Alloys 84
Ceramics
85
Development of cermets 85
Effect of heating rate on the beryllium oxide blocks for the ARE
9. HEAT TRANSFER AND PHYSICAL PROPERTIES
86
Thermal Conductivity
86
Density and Viscosity
88
Heat Capacities of Liquids
88
Surface Tensions of Fluorides
88
Vapor Pressures of Fluorides
88
Velocity Distributions in Thermal Convection Loops 89
Forced-Convection Heat Transfer with NaF-KF-LiF 90
High-Temperature Reactor Coolant Studies 91
Turbulent Convection in Annuli
91
Circulating-Fuel Heat Transfer
92
Bifluid Heat Transfer Experiments 92
10. RADIATION DAMAGE
94
Irradiation of Fused Materials
94
Inpile Circulating Loops 94
Creep Under Irradiation 95
Radiation Effects on Thermal Conductivity 96
11. ANALYTICAL STUDIES OF REACTOR MATERIALS 97
Chemical Analyses of Fluorides and Their Contaminants
97
Determination of oxygen in metallic oxides with bromine trifluoride
85
97
Volumetric determination of zirconium
98
Determination of uranium trifluoride and metallic zirconium
Calorimetric determination of zirconium
98
"Tiron" as a reagent for the determination of uranium
Petrographic Examination of Fluorides
99
Summary of Service Chemical Analyses
100
12. FLUORIDE FUEL REPROCESSING
Dissolution of ARE Fuel 101
Solvent Extraction
102
Corrosion in Dissolution of ARE Fuel
Plant Processing 103
98
99
101
102
PART III. SHIELDING RESEARCH
INTRODUCTION AND SUMMARY
107
13. BULK SHIELDING FACILITY
108
Neutron Spectra for the Divided Shield
108
Energy per Fission and Power of the Bulk Shielding Reactor 108
Gamma-Ray Air-Scattering Calculations
109
Differential results
111
Integral results 113
14. LID TANK FACILITY
119
Reflector-Moderated Reactor Shield Tests 119
Shield configurations
120
Gamma-ray attenuation data
120
Neutron attenuation data 121
Removal Cross Sections 122
Facility Modification
123
15. TOWER SHIELDING FACILITY
124 PART IV. APPENDIX
16. LIST OF REPORTS ISSUED DURING THE QUARTER 127
ORNL-1609
AIRCRAFT NUCLEAR PROPULSION PROJECT
QUARTERLY PROGRESS REPORT
For Period Ending September 10, 1953
FOREWORD
•
1 PART I. REACTOR THEORY AND DESIGN
INTRODUCTION AND SUMMARY
••.••• 5
1. CIRCULATING-FUEL AIRCRAFT REACTOR EXPERIMENT
7
The Experimental Reactor
•
•
7
Calculation of critical. mass
8
Reactor design 8
Reactor control 9
Flow characteristics in fuel tubes 9
External Fuel Circuits
10
Fuel system design
11
Sodium system design
13
Pumps 13
Valves 13
The NaF-ZrF4-UF4 Fuel • . . . . 14
Composition
14
Physical properties
15
Fuel solvent production 15
Fuel concentrate production
17
Corrosion of Inconel
17
Instrumentation 18
Auxiliary Systems
18
Off-gas system 18
Electrical system 18
Gas monitoring system
18
2. EXPERIMENTAL REACTOR ENGINEERING 20
Pumps for High-Temperature Liquids
20
Frozen-sodium-sealed pump for sodium
20
Gas-sealed sump pump for the ARE
21
Combination packed-frozen sealed pump for fluorides
22
Frozen-lead-sealed pump for fluorides
23
Allis-Chalmers canned-rotor pump 23
Rotary-Shaft and Valve-Stem Seals for Fluorides
23
Spiral-grooved graphite-packed shaft seals 23
Annular-grooved shaft seal
24
V-ring seal
24
Graphite-BeF2 packing 24
Bronze-wool and MoS2-packed frozen seal 25
Bronze-wool, graphite, and MoS2-packed frozen seal
25
Copper-braid and MoS2-packed seal test
25
Frozen-lead seal 26
Vitreous seals
26
Graphitar-Graphitar shaft seal
27
Packing-penetration tests 28
High-Temperature Bearing Development Program
Instrumentation 29
Fluoride leak detection
29
28
Sodium leak detection
29
Flow measurement
30
3. AIRCRAFT REACTOR DESIGN STUDIES
31
Shield Designs for Reflector-Moderated Reactors
31
Comparative Analyses of Liquid Metal Coolants
37
Activation of rubidium, potassium, and sodium
37
Effect of secondary coolant on power plant weight 37
Power Plant Performance and Control
38
Description of power plant
39
Design performance
43
System characteristics that affect reactor control
43
4. UNIFORM THERMAL-NEUTRON FLUX REACTOR
Critical. Mass
47
Neutron Flux
49
Importance Function
50
PART II. MATERIALS RESEARCH
INTRODUCTION AND SUMMARY
53
5. CHEMISTRY OF' HIGH-TEMPERATURE LIQUIDS
Thermal Analysis of Fluoride Fuels
55
NaF'-ZrF4-UF4 56
KF-Z rF4 -UF4 56
Systems containing ThF4 57
UF3 -zrF4
57
UF3 -UF4 -ZrF4 57
NaF-ZrF4-UF4-UF3
57
Thermal Analysis of Chloride Fuels
57
NaC 1-UCl4
58
KCl-UCl4
58
CsCl-UCl4
59
CaCl.2-UCl4
59
Thermal Analysis of Fluoride Coolants
59
Quenching Experiments with Fluorides
59
47
55
Differential Thermoanalysis of Fluorides
61
Phase Equilibria of Fused Salts by Filtration 61
X-Ray Diffraction Studies of Fluorides
61
NaF-UF4
61
NaF-ZrF4 -UF4 . .
.
62
Fundamental Chemistry of High-Temperature Liquids
62
Spectrophotometry in fused salts 62
Thermogalvanic potentials in liquids
65
EMF measurements in fused salts 66
Production and Purification of Fluoride Mixtures
69
Treatment of NaZrF5 melts with metallic zirconium 69
Treatment of NaPeF3 with metallic beryllium
70
Reduction of dissolved chromous fluoride by hydrogen
70
Preparation of various fluorides
70
6. CORROSION RESEARCH
71
Fluoride Corrosion of Inconel in Static and Seesaw Tests . . . 72 Effect of oxide layer
Removal of oxide layer 73
Effect of oxide additives 73
Effect of small zirconium hydride additions 73
Effect of exposure time 74
Corrosion by fluorides with high UF4 concentrations 75
Corrosion of high-purity Inconel 76
Effect of temperature
76
72
Fluoride Corrosion of Inconel in Rotating Test
76
Fluoride Corrosion of Inconel in Thermal Convection Loops 76
Zirconium hydride additive
77 Effect of type 316 stainless steel insert in Inconel loop . . . 77
Effect of temperature on Inconel corrosion 77
Carbon insert in Inconel loop
78
Effect of exposure time 79
Fluoride Corrosion of Stainless Steels of Varying Purity
80
Liquid Metal Corrosion of Structural Metals 80
Rotating tests with sodium
80
Static tests with lithium 80
Dynamic tests with liquid lead in convection loops 80
Fundamental Corrosion Research 83
Oxidizing power of hydroxide corrosion products
83 Equilibrium pressure of hydrogen over sodium hydroxidemetal
systems 84
Chemical equilibria in fused salts 85
7. METALLURGY AND CERAMICS
••••••.
Welding and Brazing Research
88
Low-melting-point Nicrobraz
88
Brazing of radiator fins with LMNB
88
Nickel-chromium-phosphorous brazing alloys
90
Brazing of radiator assemblies with Nicrobraz
94
Brazing of radiator assemblies with G-E alloy No. 62
High Conductivity Metals for Radiator Fins 95
Vapor plated chromium and nickel on copper
96
Chromium-plated copper 96
Inconel clad copper
96
Type 310 stainless steel-clad copper
96
Type 446 stainless steel-clad copper
96
Copper clad with copper-aluminum alloy
96
Mechanical Properties of Inconel 97
Creep and stress-rupture tests
97
'Tube-burst tests 97
Fabrication of Pump Seals
98
Hot-pressed pump seals 98
Vitreous seals
98
Tubular Fuel Elements
99
Inflammability of Sodium Alloys 100
8. HEAT TRANSFER AND PHYSICAL PROPERTIES
101
Viscosity of Fluorides
103
Density of Fluorides
104
Electrical Conductivity of Liquids 104
Thermal Conductivity
104
Diatomaceous earth
104
Development of thermal conductivity measuring devices
Vapor Pressure of Fluorides
106
Forced-Convection Heat Transfer with NaF-KF-LiF Eutectic
Circulating-Fuel Heat Transfer
107
Bifluid Heat Transfer Experiments 109
9. RADIATION DAMAGE
111
Irradiation of Fused Materials
ill
Analyses of irradiated fuel
111
Examination of irradiated fuel containers
112
In-Pile Circulating Loops 113
87
95
101 Enthalpy and Heat Capacity of Halides
105
106
Sodium-Beryllium Oxide Stability Test
Creep Under Irradiation 115
113
L
10. ANALYTICAL STUDIES OF REACTOR MATERIALS 118
Analytical Cherr stry of Reactor Materials
118 Determination of zirconium by differential
spectrophotometry . . 118
Determination of chromium and chromium trifluoride
119
Determination of UF3 and UF4
119
Determination of oxygen in metallic oxides 120
Petrographic Examination of Fluorides
120
Summary of Service Chemical Analyses
121
PART III. SHIELDING RESEARCH
INTRODUCTION AND SUMMARY
125
11. BULK SHIELDING FACILITY
126
Tower Shielding Reactor Critical Experiment
126
Gamma-Ray Air-Scattering Calculations
126
12. LID TANK FACILITY ..
.
128
Reflector-Moderated-Reactor Shield Tests 1.28
Gamma-ray attenuation data
135
Neutron Attenuation Data 137
Shield Investigations for GE-ANP . .
s
142
Investigation of Shielding Properties of Uranium
142
Removal Cross Sections 145
13. TOWER SHIELDING FACILITY
149
14. SHIELDING THEORY
151 Neutron Spectra . . 151 Neutron Streaming in Iron . . 151
The 1953 Summer Shielding Session
151
PART IV. APPENDIX
15. LIST OF REPORTS ISSUED DURING THE QUARTER 157
ORNL-1649
AIRCRAFT NUCLEAR PROPULSION PROJECT
QUARTERLY PROGRESS REPORT
For Period Ending December 10, 1953
FOREWORD
1
PART I. REACTOR THEORY AND DESIGN
INTRODUCTION AND SUMMARY
5
1. CIRCULATING-FUEL AIRCRAFT REACTOR EXPERIMENT
The Experimental Reactor
Control rod sleeves
Reactor control
Flow in fuel tubes
Fuel tube cleaning
Reactor Physics
Critical mass
Effect of delayed neutrons
Xenon poisoning
The NaF-ZrF4-UF4 Fuel
Physical properties
Fuel production
Corrosion of Inconel
Pumps
Prototype sodium pump test
Pump auxiliaries
Impeller fabrication
Acceptance tests
Fluid Circuits
Fuel system
Sodium system
Valves
Auxiliary systems
Instrumentation
Reactor and Fluid Circuit Cleaning
Fuel Recovery and Reprocessing
Transportation of fuel
Rate of dissolution of ARE fuel
Molten fuel dissolution
6
6
8
8
8
8
12
12
12
12
13
13
13
14
15
15
15
16
16
16
16
16
16
19
19
19
20
20
21
22
2. EXPERIMENTAL REACTOR ENGINEERING
Pumps for High Temperature Liquids
Frozen-sodium-sealed pump for sodium
Gas-sealed sump pump for in-pile loop test
Magnetic-torque-transmitter pump
Rotary-Shaft and Valve-Stem Seals for Fluorides
Graphite-packed seal for spiral-grooved shaft
Graphite-BeF2 packed seals
V-ring seal
Bronze-wool, graphite, and MoS2-packed frozen seal
22
23
23
23
24
24
24
24
24
25
Packed seals for valve stems
High-Temperature Bearing Development
Materials compatibility tests
Bearing characteristics
Heat Exchanger Test
Forced-Circulation Corrosion Loop
25
25
25
26
28
29
3. REFLECTOR-MODERATED REACTOR DESIGN STUDIES
Reactor Physics
Fuel Composition and Properties
Moderator Regions
Hydrodynamics of the Fuel Circuit
Pump Design
Pressure Shell
Fuel-to-NaK Heat Exchanger
Reactor Controls
Shielding
Filling and Draining of the Reactor
31
31
33
33
38
39
41
42
42
43
43
4. CRITICAL EXPERIMENTS
44
PART II. MATERIALS RESEARCH
INTRODUCTION AND SUMMARY
47
5. CHEMISTRY OF HIGH-TEMPERATURE LIQUIDS
Thermal Analysis of Fluoride Systems
NaF-ZrF4-UF4
RbF-LiF-UF4
NaF-ThF4
LiF-RbF-BeF2
RbF-BeF2-ZrF4
Thermal Analysis of Chloride Systems
LiCl-UCl3
NaCl-UCl3
KCl-UCl3
RbCl-UCl3
CsCl-UCl3
KCl-LiCl-UCl3
RbCl-UCl4
CsCl-UCl4
KCl-LiCl-UCl4
NaCl-LiCl-UCl4
Quenching Experiments with the NaF-ZrF4 System
Differential Thermoanalysis of the NaF-ZrF4 System
Filtration Analysis of Fluorides
Mixtures with 53 mole % NaF
Mixtures with 50 mole % NaF
Mixtures with 75 mole % NaF
Fundamental Chemistry
Spectrophotometry of supercooled fused salts
EMF measurements in fused salts
Physical chemistry of fused salts
Production of Purified Fluorides
Laboratory-scale production of molten fluorides
49
49
49
50
50
51
51
51
51
51
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52
52
52
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54
54
55
55
55
55
56
56
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58
59
59
Purification of small fluoride samples for phase studies
Production of enriched material for in-pile loop experiment
Experimental production facilities
Reduction of Na2UF6 by hydrogen
Treatment of molten NaZrF5 with strong reducing agents
Reduction of NiF2 by hydrogen
Preparation of various fluorides
Purification and Properties of Hydroxides
Purification of hydroxides
Reaction of sodium hydroxide with carbonaceous matter
59
59
60
60
60
61
62
63
63
63
6. CORROSION RESEARCH
Fluoride Corrosion in Static and Seesaw Tests
Inconel corrosion by fluorides with metal fluoride additives
Corrosion of various metal combinations
Corrosion of cermets
Inconel with oil and trichloroethylene additives
Inconel corrosion by fluorides with MoS2 additive
Screening tests of metallic bearing materials
Fluoride Corrosion of Inconel in Thermal Convection Loops
Effect of fluoride batch purity
Effect of chromium additives
Pretreatment of fluoride with Inconel
Effect of exposure time
Effect of temperature
Effect of surface-to-volume ratio
Fluoride with 6.5 mole % UF4
The fluoride NaZrF5
Fluoride Corrosion of Nickel and Stainless Steel Loops
Liquid Metal Corrosion
Mass transfer in liquid lead
Static tests of BeO in sodium, lithium, and lead
Spinner tests of Inconel and type 405 stainless steel in sodium
Static tests of bearing materials in sodium, lithium, and lead
Static tests of stainless steels in lithium
Static tests of solid fuel elements in sodium and sodium hydroxide
Fundamental Corrosion Research
Oxidizing power of hydroxide corrosion products
Equilibrium pressure of hydrogen in hydroxide-metal systems
Mass transfer of chromium in Inconel-fluoride systems
64
65
65
65
66
67
67
67
67
67
71
72
72
72
72
72
73
73
74
74
75
75
76
76
76
80
80
80
82
7. METALLURGY AND CERAMICS
Welding and Brazing Research
Brazing of radiator assemblies
Brazing of high-conductivity radiator fins
"Electroless" preplating of brazing alloys
Inert-arc welding of solid fuel elements
Mechanical Properties of Inconel
Stress-rupture of Inconel in fluoride fuel
Tube-burst tests of triaxially stressed tubes
Environmental effects on creep of Inconel
High-Conductivity Metals for Radiator Fins
Diffusion barriers
Clad copper
Electroplated copper
Solid phase bonding
83
84
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86
89
89
91
91
91
92
92
93
93
93
93
Fabrication of Special Materials
Extrusion of Inconel-type alloys
Rolling of chromium-cobalt alloy
Rolling of cobalt
Rolling of iron-chromium-nickel alloy
Cold-rolled columbium alloy
Tubular Fuel Elements
Ceramic Research
Glass-type pump seals
Ceramic container for fuel
High-density graphite
Combustion of Sodium Alloys
93
93
94
94
94
94
94
96
96
96
96
96
8. HEAT TRANSFER AND PHYSICAL PROPERTIES RESEARCH
Heat Capacity
Thermal Conductivity of Solidified Salts
Density and Viscosity of Fluorides
Vapor Pressures of Fluorides
Electrical Conductivity of Fluorides
Forced Convection Heat Transfer with NaF-KF-LiF Eutectic
Flow in Thermal-Convection Loops
Fluid Flow in an Annulus
Transient Surface-Boiling Studies
Circulating-Fuel Heat Transfer
97
97
98
98
99
99
100
101
102
102
102
9. RADIATION DAMAGE
Irradiation of Fuel Capsules
Creep Under Irradiation
In-Pile Circulating Loops
103
103
104
106
10. ANALYTICAL STUDIES OF REACTOR MATERIALS
Analytical Chemistry of Reactor Materials
Oxidation states of iron
Oxidation states of chromium
Determination of UF3 and UF4
Reducing power of NaZrF5 with zirconium addition
Dissolution of fluoride mixtures containing zirconium
Petrographic Examination of Fluorides
Mass Spectrometer Investigations of Irradiated Fluoride Fuels
Calculation of UF4 in unirradiated fuels
Calculation of U235 lost from irradiated fuel
Determination of U235 burnup
Summary of Service Chemical Analyses
107
107
107
108
108
109
109
109
110
110
111
111
112
PART III. SHIELDING RESEARCH
INTRODUCTION AND SUMMARY
115
11. BULK SHIELDING REACTOR
Spectrum of Gamma Rays Emitted by the BSR
Spectrometer arrangement
Results
Fast-Neutron Leakage Spectra of the BSR
116
116
116
116
117
12. LID TANK FACILITY
120
Slant Penetration of Neutrons Through Water
Air Duct Tests
Removal Cross Sections
Survey of Lid Tank Experiments
120
121
122
123
13. TOWER SHIELDING FACILITY
125
14. SHIELDING ANALYSIS
Visible Light from a Nuclear Power Plant
Neutron Reflection Coefficient for Water
126
126
126
PART IV. APPENDIXES
15. LIST OF REPORTS ISSUED DURING THE QUARTER
129
16. DIRECTORY OF ACTIVE ANP RESEARCH PROJECTS AT ORNL
131
ORGANIZATION CHART
139
ORNL-1692
AIRCRAFT NUCLEAR PROPULSION PROJECT
QUARTERLY PROGRESS REPORT
For Period Ending March 10, 1954
FOREWORD
vii
SUMMARY
1
PART I. REACTOR THEORY AND DESIGN
1. CIRCULATING-FUEL AIRCRAFT REACTOR EXPERIMENT
The Experimental Reactor System
Reactor Physics
Neutron temperature
Criticality in the ARE fill-and-flush tank
The ARE critical experiment
Production of Fuel Concentrate
Pumps
Acceptance test program
Pump assembly
Impeller fabrication and testing
Fuel Recovery and Reprocessing
Fuel dissolution
Solvent extraction processing
7
7
8
8
8
9
9
10
10
11
11
12
12
13
2. EXPERIMENTAL REACTOR ENGINEERING
In-Pile Loop Component Development
Vertical-shaft sump pump
Pump with a centrifugal seal
Horizontal-shaft sump pump
Heat Exchanger and Radiator Tests
Heat exchanger test
Sodium-to-air radiator test
Forced-Circulation Loops
Air-cooled loop
Beryllium-NaK compatibility test
Bifluid heat transfer loop
High-Temperature Bearing Development
Materials compatibility tests
Bearing tester design
Rotary-Shaft and Valve-Stem Seals for Fluorides
Spiral-grooved graphite-packed shaft seals
Graphite-BeF2 packed seal
V-ring seal
Chevron seal
Graphite-BaF2 packed seal
Shaft seal for in-pile pump
Packing penetration tests
Valve-stem packing tests
Self-Bonding Tests of Materials in Fluoride Mixtures
Removal of Fluoride Mixtures from Equipment
15
15
15
15
17
18
18
18
19
19
20
20
22
22
22
22
22
23
24
24
25
26
26
26
27
27
3. REFLECTOR-MODERATED REACTOR
Effects of Reactor Design Conditions on Aircraft Gross Weight
Core Flow Experiment
Reactor Calculations
Reactor Dynamics
Computational Techniques
Beryllium Cross Sections
Chemical Processing of Fluoride Fuel by Fluorination
28
28
37
39
40
40
41
42
4. CRITICAL EXPERIMENTS
Supercritical-Water Reactor
Air-Cooled Reactor
Reflector-Moderated Reactor
45
45
45
45
PART II. MATERIALS RESEARCH
5. CHEMISTRY OF HIGH-TEMPERATURE LIQUIDS
Thermal Analysis of Fluoride Systems
NaF-LiF-ZrF4-UF4
NaF-BeF2-ZrF4-UF4
NaF-LiF-BeF2-UF4
Thermal Analysis of Chloride Systems
RbCl-UCl3
NaCl-ZrCl4
Quenching Experiments with Fluoride Systems
NaF-UF4
NaF-ZrF4
Filtration Analysis of Fluoride Systems
NaF-ZrF4
NaF-ZrF4-UF4
NaF-KF-ZrF4-UF4
Production of Purified Fluoride Mixtures
Laboratory-scale production and purification of fluoride mixtures
Purification of fluoride mixtures for phase studies
Experimental production facilities
Production-scale facility
Purification and Properties of Hydroxides
Purification of hydroxides
Reaction of sodium hydroxide with carbon
Chemical Reactions in Molten Salts
Chemical equilibria in fused salts
Formation of UF3 in NaF-ZrF4 melts
Treatment of molten NaZrF5 with strong reducing agents
Reduction of NiF2 and FeF2 by hydrogen
Spectrophotometry of supercooled fused salts
EMF measurements in fused salts
49
49
50
50
50
50
51
52
52
52
53
54
54
54
55
55
55
55
55
56
56
56
56
56
56
60
61
62
62
63
6. CORROSION RESEARCH
Fluoride Corrosion in Static and Tilting-Furnace Tests
Effect of methods of manufacturing the fuel on the corrosion of Inconel
Corrosion of ceramic materials
Effect of graphite additions
Effect on nickel and Inconel rods exposed to fluoride mixtures in air
Thermal Convection Loop Design and Operation
Fluoride Corrosion of Inconel in Thermal Convection Loops
Effect of exposure time on depth of attack
65
66
66
66
66
67
67
68
68
Effect of exposure time on chemical stability of the fluorides
Effect of exposure time on corrosion by nonuranium-bearing fluorides
Effect of variation in uranium concentration
Effect of temperature
Effect of variations in loop size and composition
Effect of additions to the fluorides
Corrosion of various metal combinations
Fluoride Corrosion of Stainless Steel, lzett Iron, and Hastelloy Loops
Corrosion by High-Velocity High-Temperature Fluorides
Forced-circulation corrosion loop
Oscillating-furnace studies
Static Tests of Brazing Alloys in Fluorides and Sodium
Mass Transfer in Liquid Lead
69
69
70
71
71
72
73
73
74
74
75
75
77
7. METALLURGY AND CERAMICS
Mechanical Properties of Metals
Stress-rupture tests of Inconel
Creep Tests of Columbium
Brazing Research
High-conductivity radiator fins
Fluoride-to-air radiator
Helium-atmosphere brazing
Nickel-phosphorus brazing alloy
Nickel-germanium brazing alloy
High-Conductivity Metals for Radiator Fins
Diffusion barriers
Diffusion couples
Commercially clad copper
Fabrication of Special Materials
Clad columbium disks
Clad molybdenum and columbium tubing
Drawn tubular fuel elements
Ceramic Research
Ceramic container for fluoride fuel
Ceramic pump bearings
Boron carbide-iron cermets
84
84
84
87
87
87
89
89
90
90
91
91
91
91
92
92
93
93
93
93
94
94
8. HEAT TRANSFER AND PHYSICAL PROPERTIES
Physical Properties Measurements
Heat capacity
Thermal conductivity
Density, viscosity, and surface tension
Electrical conductivity of molten salts
Fused-Salt Heat Transfer
Hydrodynamics Research
Circulating-Fuel Heat Transfer
95
95
95
95
97
98
98
98
99
9. RADIATION DAMAGE
Radiation Stability of Fused-Salt Fuels
Petrographic examination of fuels
Temperature control in static capsule tests
Miniature circulating loops
Stress-Corrosion Apparatus
Creep Under Irradiation
LITR Fluoride-Fuel Loop
102
102
102
102
103
103
103
105
10. ANALYTICAL STUDIES OF REACTOR MATERIALS
Analytical Chemistry of Reactor Materials
Oxidation states of chromium and iron in ARE fuel solvent, NaZrF5
Oxidation states of chromium and uranium in ARE fuel solvent, NaZrF5
Separation of UF4 from UF3
Fluoride Fuel Investigations
Summary of Service Chemical Analyses
107
107
107
108
109
112
112
PART III. SHIELDING RESEARCH
11. SHIELDING ANALYSIS
Estimates of Removal Cross Sections Based on the Continuum Theory of
the Scattering of Neutrons from Nuclei
Critique of Lithium Hydride as a Neutron Shield
115
12. LID TANK FACILITY
Air-Duct Tests
Shielding Tests for the Reflector-Moderated Reactor
Lid tank dose measurements corrected to designed reflector-moderated reactor shield
Shield weight calculations
Removal Cross Sections
Instrumentation
117
117
117
118
120
122
122
13. BULK SHIELDING FACILITY
G-E Test Fixture Duct Experiment
GE-ANP Shield Mockup Experiments
123
123
124
14. TOWER SHIELDING FACILITY
Facility Construction
Radiation Detection Equipment
Thermal-neutron flux
Fast-neutron dose
Gamma-ray dose
Other gamma-ray detectors
Isodose plotter
Estimate of Neutron and Gamma Radiation Expected at the Tower Shielding Facility
135
135
135
135
135
135
136
136
137
115
116
PART IV. APPENDIX
15. LIST OF REPORTS ISSUED DURING THE QUARTER
141
ORNL-1729
AIRCRAFT NUCLEAR PROPULSION PROJECT
QUARTERLY PROGRESS REPORT
For Period Ending June 10, 1954
FOREWORD
vii
SUMMARY
1
PART I. REACTOR THEORY AND DESIGN
1. CIRCULATING-FUEL AIRCRAFT REACTOR EXPERIMENT
The Experimental Reactor System
Pumps
Heat exchangers
Fluid circuits
Fuel-enrichment system
Loading facilities
Fuel-sampling facility
Fuel-unloading facility
Reactor control
Fuel System Mock-up Tests
Operation of the Fuel System
Cleaning
Pressure filling
Pressure and flow characteristics
Functional tests
Hot-gas test
Pump Fabrication and Tests
Reactor System Component Loop
Fuel Recovery and Reprocessing
7
7
7
7
8
8
8
9
10
10
10
10
11
11
11
11
12
12
14
14
2. EXPERIMENTAL REACTOR ENGINEERING
In-Pile Loop Component Development
Centrifugally sealed pump
Horizontal-shaft sump pump
Vertical-shaft sump pump
Hydraulic pump drives
Fluoride-to-water heat exchanger
Forced-Circulation Corrosion Loops
Sodium-Beryllium-Inconel Mass-Transfer Test
Fluoride-to-Sodium Heat-Exchanger Test
Gas-Furnace Heat-Source Development
Sodium Sampler
Removal of Fluoride Mixtures from Equipment
Bearing-Materials Tests
Rotary-Shaft Seals
18
18
18
19
19
21
21
21
22
22
23
24
24
24
26
3. REFLECTOR-MODERATED REACTOR
A Comparison of Lithium- and Zirconium-Base Fluoride Fuels
Reactor Physics
Reactor Calculations
28
28
32
32
PART II. MATERIALS RESEARCH
4. CHEMISTRY OF MOLTEN MATERIALS
Quenching Experiments with Fluoride Systems
NaF-ZrF4
NaF-UF4
Visual Observation of Melting Temperatures
Differential Thermal Analysis of the NaF-ZrF4 System
Filtration Analysis of Fluoride Systems
NaF-ZrF4
NaF-LiF-RbF-UF4
Thermal Analysis of Fluoride Systems
LiF-UF3
NaF-UF3
RbF-UF3
KF-LiF-UF3
RbF-LiF-UF3
NaF-ZrF4-UF4-UF3
NaF-ThF4
LiF-BeF2-ThF4-UF4
NaF-CrF3
Thermal Analysis of Chloride and Mixed Chloride-Fluoride Systems
UCl3-UCl4
UCl4-UF4
UCl3-UF3
KCl-UCl4
RbCl-UCl4
KCl-CuCl-UCl3
X-Ray Diffraction Studies of the NaF-ZrF4 System
Chemical Reactions in Molten Salts
Chemical equilibria in molten fluorides
Solubility of UF3 in NaF-ZrF4 mixtures
Solubility of UF3 in NaF-KF-LiF mixtures
Solubility of UF3 in NaF-RbF-LiF mixtures
Chlorination of UF3
Preparation of UF3·2ZrF4
Preparation of various fluorides
Fundamental Chemistry of Fused Salts
EMF measurements
Physical chemistry
Chemical Effects of Fission Products
Quantity of fission products
Separation of solid phases
Effects on viscosity and heat capacity
Effects on corrosion
Purification and Properties of Alkali Hydroxides
Purification of hydroxides
Reaction of sodium hydroxide with metals
Production of Purified Molten Fluorides
Laboratory-scale production
Experimental production
Large-scale production
Production of enriched fuel for in-pile loop
39
39
39
41
42
42
42
42
42
43
43
43
43
43
44
44
44
45
45
45
45
46
46
46
47
47
47
50
50
51
52
53
54
54
54
55
55
57
57
57
57
58
58
59
59
59
60
60
60
61
61
5. CORROSION RESEARCH
Fluoride Corrosion of Inconel in Static and Seesaw Tests
Effect of chromium addition to fluoride melt
Effect of temperature
Effect of surface area
Effect of reduced phases in fluoride melt
Effect of fission products
Static and Seesaw Tests of Various Materials in Fluoride Mixtures and Liquid Metals
Dissimilar metals in NaF-ZrF4-UF4
Molybdenum-coated Inconel in NaF-ZrF4-UF4
Stainless steel in lithium with lithium nitride added
Chromalloyed steels in liquid metals
Cermets in NaF-ZrF4-UF4
Graphite in NaF-ZrF4-UF4 and in sodium
Fluoride Corrosion of Inconel in Thermal-Convection Loops
Effects of UF3 and mixtures of UF3 and UF4 in fluoride fuels
Effect of hydrogen fluoride
Effect of temperature
Effect of exposure time
Thermal-Convection-Loop Tests of Various Materials
NaF-ZrF4-UF4 in special Inconel
NaF-ZrF4-UF4 in Hastelloy B
NaF-ZrF4-UF4 in stainless steel
NaF-ZrF4-UF4 in Inconel with stainless steel or nickel inserts
Sodium in Inconel with beryllium inserts
Lithium in stainless steel
Fundamental Corrosion Research
Mass transfer in liquid lead
Products of hydroxide-metal reactions
Dehydration of sodium hydroxide
Color changes in fused hydroxides
62
63
63
63
64
65
65
66
66
66
66
66
68
70
72
72
74
74
76
77
77
77
77
77
79
79
79
79
81
84
85
6. METALLURGY
Stress-Rupture Tests of Inconel
High-Conductivity Metals for Radiator Fins
Special Materials Research
Hastelloys B and C
Nickel-molybdenum alloys
Stainless-steel-clad molybdenum and columbium
Columbium
Boron carbide
Welding and Brazing
Brazing alloy development
Beryllium test assembly
88
89
91
91
91
93
93
93
93
94
94
97
7. HEAT TRANSFER AND PHYSICAL PROPERTIES
Physical Properties Measurements
Heat capacity
Density and viscosity
Thermal conductivity
Electrical conductivity
Vapor pressures
Fused-Salt Heat Transfer
Reactor Hydrodynamics
Heat-Removal Study of BSF Reactor
Heat Transfer in Circulating-Fuel Reflector-Moderated Reactor
99
99
99
99
100
100
101
101
102
102
103
Heat Transfer in NaOH-Moderated Circulating Fuel Reactor
103
8. RADIATION DAMAGE
Radiation Stability of Fluoride Fuels
LITR Fluoride-Fuel Loop
In-Pile Stress Corrosion and Creep
Remote Metallography
105
105
107
107
107
9. ANALYTICAL STUDIES OF REACTOR MATERIALS
Analytical Chemistry of Reactor Materials
Oxidation states of chromium and uranium in NaZrF5-base fuels
Determination of oxygen in NaZrF5-base fuels
Oxidation of trivalent uranium by hexavalent uranium
Stability of trivalent uranium in hydrochloric acid solutions
Removal of film from Inconel tubing
Determination of sulfur in natural gas
Petrographic Investigations of Fluoride Fuels
Summary of Service Analyses
109
109
109
110
111
111
111
112
112
112
PART III. SHIELDING RESEARCH
10. LID TANK FACILITY
Slant Penetrations of Neutrons Through Water
Secondary Gamma-Ray Study
117
117
118
11. BULK SHIELDING FACILITY
Gamma-Ray Air-Scattering Calculations
Thermal-Neutron-Flux Perturbation by Gold Foils in Water
Reactor Power Calibration Techniques
Leakage-Flux Changes Due to Control-Rod Settings
121
121
128
128
135
12. TOWER SHIELDING FACILITY
Experimental Program
Operation of the Reactor
136
136
136
PART IV. APPENDIX
13. LIST OF REPORTS ISSUED DURING THE QUARTER
141
ORNL-1771
AIRCRAFT NUCLEAR PROPULSION PROJECT
QUARTERLY PROGRESS REPORT
For Period Ending September 10, 1954
FOREWORD
vii
SUMMARY
1
PART I. REACTOR THEORY, COMPONENT DESIGN AND TESTING, AND CONSTRUCTION
1. CIRCULATING-FUEL AIRCRAFT REACTOR EXPERIMENT
The Experimental Reactor System
Characteristics of the Fuel and the Sodium Systems During the Water Tests
Preparations for Loading the ARE
Fuel-Concentrate Injection Nozzle
ARE Unloading Experiment
ARE Fuel Recovery and Reprocessing
ARE Pumps
Fabrication and Testing
Seal-Gas Pressure-Balancing System
Radiation Damage to Pump Drives
Radiation Damage to Shaft Seal
Motor Test
Reactor System Component Test Loop
Operation of Loop
Examination of Hairpin Tube
Reactor Physics
9
9
10
11
12
12
12
14
14
14
14
15
15
16
16
16
16
2. REFLECTOR-MODERATED REACTOR
Design of the CFRE
CFRE Component Development Projects
Reactor Physics
Reactor Calculations
Beryllium Thermal Stress Test
Beryllium-Inconel-Sodium Systems
Beryllium-Inconel-Sodium Compatibility Tests
Mass Transfer Tests in Thermal-Convection Loops
Mass Transfer Tests in Forced-Circulation Loops
17
17
18
24
24
24
29
29
30
32
3. EXPERIMENTAL REACTOR ENGINEERING
In-Pile Loop Component Development
Horizontal-Shaft Sump Pump
Vertical-Shaft Centrifugal Sump Pump
Hydraulic Motor Pump Drives
Forced-Circulation Corrosion Loops
Inconel Loops
Dissimilar Metal Loops
Gas-Furnace Heat-Source Development
Study of the Cavitation Phenomenon
Expansion and Improvement of Thermal-Convection Loop Testing Facilities
34
34
34
37
38
38
38
41
41
41
42
4. CRITICAL EXPERIMENTS
Reflector-Moderated Reactor
Supercritical-Water Reactor
44
44
47
PART II. MATERIALS RESEARCH
5. CHEMISTRY OF MOLTEN MATERIALS
Solid Phase Studies in the NaF-ZrF4-UF4 System
Visual Observation of Melting Temperatures in the NaF-UF4 System
Phase Relationships in UF3-Bearing Systems
UF3 in ZrF4-Bearing Systems
UF3 in NaF-KF-LiF Mixtures
UF3 in NaF-RbF-LiF Mixtures
UF3 in the Individual Alkali-Metal Fluorides
UF3 in Binary Alkali-Metal Fluoride Systems
Purification of Rubidium Fluoride
Chemical Reactions in Molten Salts
Chemical Equilibria in Fused Salts
Stability of Chromium Compounds in Molten Fluorides
Reduction of NiF2 by H2 in NaF-ZrF4 Systems
Reduction of FeF2 by H2 in NaF-ZrF4 Systems
Preparation of Various Fluorides
Fundamental Chemistry of Fused Salts
EMF Measurements
Solubility of Xenon in Molten Salts
X-Ray Diffraction Studies in Salt Systems
Physical Chemistry
Production of Purified Molten Fluorides
Use of Zirconium Metal as a Scavenging Agent
Purification of NaF-ZrF4 Mixtures by Electrolysis
Preparation of UF3-Bearing Fuels
Alkali-Metal Fluoride Processing Facility
Production Facility
In-Pile Loop Loading
Chemistry of Alkali-Metal Hydroxides
Purification
Reaction of Sodium Hydroxide with Metals
53
54
55
56
57
57
58
58
60
60
60
60
63
63
64
67
67
67
70
70
72
72
72
73
77
78
79
79
80
80
80
6. CORROSION RESEARCH
Static and Seesaw Corrosion Tests
Brazing Alloys in NaF-ZrF4-UF4 and in Sodium
Special Stellite Heats in NaF-ZrF4-UF4 and in Sodium
Hastelloy R in Various Media
Inconel in Molten Rubidium
Carburization of Inconel by Sodium
Special Tar-Impregnated and Fired Graphite
Ceramics in Various Media
Fluoride Corrosion of Inconel in Thermal Convection Loops
Effect of UF3 in ZrF4-Base Fuels
Effect of UF3 in Alkali-Metal Base Fuels
Effect of Zirconium Hydride Additions to Fuel
Effect of Uranium Concentration
Effect of Inconel Grain Size
Fluoride Corrosion of Hastelloy B in Thermal-Convection Loops
Lithium in Type 316 Stainless Steel
Fundamental Corrosion Research
81
82
82
83
85
86
89
90
94
95
95
96
98
98
98
98
99
100
Mass Transfer in Liquid Lead
Flammability of Sodium Alloys
Thermodynamics of Alkali-Metal Hydroxides
Chemical Studies of Corrosion
Effect of Temperature on Corrosion of Inconel and Type 316 Stainless Steel
Corrosion by Fission Products
Controlled-Velocity Corrosion Testing Apparatus
Reaction Between Graphite and Fluoride Melt
Lithium Fluoride Castings
100
102
102
108
108
109
109
110
110
7. METALLURGY
Stress-Rupture Tests of Inconel
High-Conductivity-Fin Sodium-to-Air Radiator
Investigations of Fin Materials
Development of Brazing Alloys for Use in Fabricating Radiators
Radiator Fabrication
Nozzles for the Gas-Fired Liquid-Metal-Heater System
Special Materials Fabrication Research
Stainless-Steel-Clad Molybdenum and Columbium
Inconel-Type Alloys
Nickel-Molybdenum-Base Alloys
Duplex Tubing
Sigma-Phase Alloys
Boron Carbide Shielding
Tubular Fuel Elements
Metallographic Examination of a Fluoride-to-Sodium Heat Exchanger
111
112
116
117
118
120
120
121
121
122
122
123
124
124
124
124
8. HEAT TRANSFER AND PHYSICAL PROPERTIES
Physical Properties Measurements
Heat Capacity
Density and Viscosity
Thermal Conductivity
Electrical Conductivity
Vapor Pressure
Fused-Salt Heat Transfer
Transient Boiling Research
Fluid Flow Studies for Circulating-Fuel Reactors
Heat Transfer Studies for Circulating-Fuel Reactors
127
127
127
127
129
129
129
130
130
131
131
9. RADIATION DAMAGE
MTR Static Corrosion Tests
Fission Product Corrosion Study
Facilities for Handling Irradiated Capsules
Analysis of Irradiated Fluoride Fuels for Uranium
High-Temperature Check Valve Tests
Miniature In-Pile Loop - Bench Test
Life Tests on an RPM Meter, Bearings, and a Small Electric Motor Under Irradiation
Removal of Xenon from Fused Fluorides
C7F16-UF6 Irradiation
LITR Horizontal-Beam-Hole Fluoride-Fuel Loop
ORNL Graphite Reactor Sodium-Inconel Loop
Creep and Stress-Corrosion Tests
Remote Metallography
Fission-Fragment Annealing Studies
High-Temperature, Short-Time, Grain-Growth Characteristics of Inconel
BNL Neutron Spectrum - Radiation Damage Study
134
134
135
135
136
137
137
137
140
140
141
142
142
144
145
145
145
MTR Neutron-Flux Spectra - Radiation Damage Study
10. ANALYTICAL STUDIES OF REACTOR MATERIALS
Analytical Chemistry of Reactor Materials
Determination of Oxygen in Fluoride Fuels
Oxidation-Reduction Titrations in Fused Salts
Polarographic Studies in Fused Ammonium Formate
Conversion of UF3 and UF4 to the Respective Chlorides with BCl3
Solubility of Tri- and Tetravalent Uranium Fluorides in Fused NaAlCl4
Oxidation of UF3 with Oxygen
Determination of Lithium, Potassium, Rubidium, and Fluoride Ion
in NaF-KF(RbF)-LiF-Base Fuels
Oil Contamination in ARE Helium
Petrographic Investigations of Fluoride Fuels
Summary of Service Analyses
147
148
148
148
150
150
151
151
152
152
154
154
154
PART III. SHIELDING RESEARCH
11. SHIELDING ANALYSIS
Slant Penetration of Composite Slab Shields by Gamma Rays
Air Scattering of Neutrons
Single Anisotropic Air Scattering in the Presence of the Ground (Shielded Detector)
Single Isotropic Air Scattering in the Presence of the Ground (Unshielded Detector)
Formulas for Multiple Scattering in a Uniform Medium
Ground Scattering of Neutrons
Focusing of Radiation in a Cylindrical Crew Compartment
157
157
158
158
158
159
162
163
12. LID TANK SHIELDING FACILITY
Reflector-Moderated Reactor and Shield Mockup Tests
Effective Removal Cross Section of Carbon
GE-ANP Helical Air Duct Experimentation
164
164
164
166
13. BULK SHIELDING FACILITY
Reactor Radiations Through Slabs of Graphite
Reactor Air Glow
Fuel Activation Method for Power Determination of the ARE
168
168
170
173
14. TOWER SHIELDING FACILITY
Fast-Neutron Ground and Air Scattering Measurements
Calorimetric Reactor Power Determination
GE-ANP R-1 Divided-Shield Mockup Tests
175
175
175
178
PART IV. APPENDIXES
15. LIST OF REPORTS ISSUED DURING THE QUARTER
183
ORGANIZATION CHART OF THE AIRCRAFT NUCLEAR PROPULSION PROJECT
185
ORNL-1816
AIRCRAFT NUCLEAR PROPULSION PROJECT
QUARTERLY PROGRESS REPORT
For Period Ending December 10, 1954
FOREWORD
v
SUMMARY
1
PART I. REACTOR THEORY, COMPONENT DEVELOPMENT, AND CONSTRUCTION
1. CIRCULATING-FUEL AIRCRAFT REACTOR EXPERIMENT
Operation of the Aircraft Reactor Experiment
Low-power experiments
High-power experiments
Mathematical analysis of approach to critical
Operation of ARE Pumps
Loading of the ARE
Analysis of Leak in Sodium System
Preliminary Estimates of Corrosion in ARE
11
11
12
13
15
15
18
18
19
2. REFLECTOR-MODERATED REACTOR
Expansion-Tank and Xenon-Removal System
Control Rod Design Considerations
Fill and Drain System
Design Physics
Activation of the Inconel core shells
Mathematical models for reflector-moderated reactors
Proposed ART Installations
21
21
24
25
26
26
28
29
3. EXPERIMENTAL REACTOR ENGINEERING
In-Pile Loop Component Development
Horizontal-shaft sump pump
Heat exchanger
Pump Development Program
ARE-type sump pumps
Large-scale pump development
Design and Operation of Forced-Circulation Corrosion and Mass-Transfer Tests
Fused salts in Inconel
Beryllium-sodium-Inconel mass transfer
Sodium in multimetal loops
Natural-gas heat sources for forced-circulation loops
Heat Exchanger Development
Heat exchanger tests
Header leak test
Pump for heat exchanger tests
Gas-Furnace Heat Source Development
Sodium-cooled 100-kw furnace tests
Natural-gas burner
Trap for Fluoride Vapors
41
41
41
43
43
43
43
44
44
45
45
46
46
46
46
46
47
47
50
50
4. CRITICAL EXPERIMENTS
Reflector-Moderated Reactor
52
52
PART II. MATERIALS RESEARCH
5. CHEMISTRY OF MOLTEN MATERIALS
Phase Equilibrium Studies
Solid phase studies in the NaF-Zr4-UF4 system
Phase relationships in UF3-bearing systems
Solubility of UF4 in NaF-KF-LiF eutectic
UF3 stability
Differential thermal analysis
Chemical Reactions in Molten Salts
Reduction of FeF2 by H2 in NaF-ZrF4 systems
Reduction of UF4 to UF3 in fluoride melts
Electrochemistry of fused salts
Stability of chromous and ferrous fluorides in molten fluorides
Reduction of UF4 by structural metals
Production of Purified Molten Fluorides
Electrolytic purification of zirconium-base fluorides
Fluoride production facility
Alkali fluoride processing facility
Purification of KF and RbF
Preparation of various fluorides
Chemistry of Alkali Hydroxides
Purification of hydroxides
Effect of additives on hydrogen pressure over NaOH-Ni system
Fundamental Chemistry of Fused Salts
Solubility of xenon in fused salts
X-ray diffraction studies in salt systems
Physical chemistry
Viscosity measurements
57
57
57
58
59
60
61
61
61
61
62
63
64
66
66
68
69
70
71
71
71
71
72
72
72
73
75
6. CORROSION RESEARCH
Thermal-Convection Loop Corrosion Studies
Inconel loop containing UF3 in alkali-metal-base mixtures
Type 316 stainless steel loops containing UF3 in alkali-metal-base mixtures
Effect of induced potentials
Hastelloy B thermal-convection loops
Special alloy thermal-convection loops
Sodium-Beryllium-Inconel Compatibility
Static Corrosion Studies
Brazing alloys on stainless steel
Brazing alloys on nickel
Screening tests of carbides
Magnesium-lithium alloy in water
Rubidium Investigations
Fundamental Corrosion Research
Mass transfer in liquid lead
Fused hydroxides as acid-base analog systems
Flammability of alkali metal solutions at high temperatures
Chemical Studies of Corrosion
Effect of temperature on the corrosion of Inconel melts with NiF2 additions
Effect on chromium additions on the corrosion of Inconel and fluoride melts with
NiF2 additions
Effect of chromium valence state on corrosion of Inconel
76
76
76
76
77
77
77
78
80
80
80
82
86
87
88
88
92
96
98
98
98
99
7. METALLURGY AND CERAMICS
Development of Nickel-Molybdenum Base Alloys
Fabrication experiments
New alloys
Oxidation and oxidation protection
Radiator fabrication
Welding
Mechanical properties studies
Special Materials Fabrication
Duplex tubing
Boron carbide shielding
Tubular fuel elements
Control rods
Al-UO2 elements for shielding experiment
Brazing Alloy Development
Heat Exchanger Fabrication
Beryllium Oxide Fuel Elements
100
100
100
102
103
103
104
106
107
107
107
108
108
108
108
109
111
8. HEAT TRANSFER AND PHYSICAL PROPERTIES
Fused Salt Heat Transfer
In-Pile Loop Heat Exchanger Analysis
Free Convection in Fluids with Volume Heat Sources
Heat Transfer Effectiveness of Reactor Coolants
ART Core Hydrodynamics
ART Heat Transfer
Physical Properties Measurements
Heat capacity
Viscosity
Thermal conductivity
112
112
112
113
114
114
115
116
116
117
117
9. RADIATION DAMAGE
MTR Static Corrosion Tests
Effect of Irradiation on UF6-C7F16
Miniature In-Pile Loop
Bench test
Heat transfer calculations
Removal of 135Xe from Molten Fluoride Fuels
LITR Horizontal-Beam-Hole Fluoride-Fuel Loop
Creep and Stress-Corrosion Tests
Remote Metallography
Mass Spectrographic Analyses
120
120
121
122
122
122
124
125
126
127
127
10. ANALYTICAL STUDIES OF REACTOR MATERIALS
Analytical Chemistry of Reactor Materials
Determination of uranium metal in fluoride salt mixtures
Determination of trivalent uranium in fluoride fuels
Determination of oxygen in fluoride fuels
Determination of sulfur
Determination of fluoride in NaF-KF-LiF-base fuels
Petrographic Investigations of Fluoride Fuels
ANP Service Laboratory
129
129
129
129
131
131
132
133
133
11. RECOVERY AND REPROCESSING OF REACTOR FUEL
Fission-Product Removal
Applications of Fused Salt-Volatility Processes
Aircraft reactor fuels
Heterogeneous reactor fuels
134
134
137
138
138
PART III. SHIELDING RESEARCH
12. SHIELDING ANALYSIS
Slant Penetration of Composite Slab Shields by Gamma Rays
Emergy Absorption Resulting from Incident Gamma Radiation as a Function of
Thickness of Materials with Slab Geometry
A Formulation for Radiation Injury to Include Time Effects
Analysis of Some Preliminary Differential Experiments
Interpretation of Air and Ground Scattering at the Tower Shielding Facility
143
143
13. LID TANK SHIELDING FACILITY
Effective Neutron Removal Cross Section of Lithium
GE-ANP Helical Air Duct Experimentation
Reflector-Moderated Reactor and Shield Mockup Tests
151
151
153
155
14. BULK SHIELDING FACILITY
A Search for Short-Half-Life Nuclear Isomers in 39K, 85Rb, 87Rb, and 90Zr
156
156
15. TOWER SHIELDING FACILITY
TSF Experiment with the Mockup of the GE-ANP R-1 Shield Design
158
158
144
145
146
147
PART IV. APPENDIX
ORGANIZATION CHART OF THE AIRCRAFT NUCLEAR PROPULSION PROJECT
167
ORNL-1896
AIRCRAFT NUCLEAR PROPULSION PROJECT
QUARTERLY PROGRESS REPORT
For Period Ending June 10, 1955
FOREWORD
v
SUMMARY
1
PART I. REACTOR THEORY, COMPONENT DEVELOPMENT, AND CONSTRUCTION
1. REFLECTOR-MODERATED REACTOR
Aircraft Reactor Test Design
ART Control
Control Principles
Operating Procedure
Reactor Physics
Probable Effect of Replacing Inconel by Columbium in the ART Core Shells
ART Temperature Coefficient
Reactivity Effect of a Heat Exchanger Leak
Burnup and Gamma-Ray Heating of Control Rod
15
15
17
18
19
20
20
20
21
22
2. EXPERIMENTAL REACTOR ENGINEERING
In-Pile Loop Component Development
Flux Measurements
Fission-Gas Holdup
Bench Test
Horizontal-Shaft Sump Pump
Instrumentation
Assembly of MTR In-Pile Loop No. 1
Development and Operation of Forced-Circulation Corrosion and Mass Transfer Tests
Operation of Fused Salt-Inconel Loops
Sodium in Multimetal Loops
Pump Development
Water Performance Tests
Bearing and Seal Tests
Mechanical Shakedown Tests
Short-Circuit Pump-Test Stand
Heat Exchanger Tests
Heat Exchanger Tube-Spacer Pressure-Drop Tests
Intermediate Heat Exchanger Tests
Small Heat Exchanger Tests
Core Flow Test
Thermal-Cycling Tests of Sodium-Inconel-Beryllium System
Gas-Fired Heat Source
26
26
26
26
27
27
29
29
30
30
31
32
32
33
34
35
35
35
37
37
37
39
42
3. CRITICAL EXPERIMENTS
Room-Temperature Reflector-Moderated-Reactor Critical Experiments
Reactivity Measurements
Power Distributions
Assembly for High-Temperature Critical Experiment
43
43
43
46
48
PART II. MATERIALS RESEARCH
4. CHEMISTRY OF REACTOR MATERIALS
Phase Equilibrium Studies
The Binary System LiF-ZrF4
The Ternary System NaF-LiF-ZrF4
The Quaternary System NaF-LiF-ZrF4-UF4
BeF2-Bearing Systems
Visual Observation of Fluoride Melts
Phase Separation by Zone Melting
Chemical Reactions in Molten Salts
Equilibrium Reduction of FeF2 by H2 in NaZrF5
Reduction of UF4 by Structural Metals
Stability of Chromium and Iron Fluorides in Molten Fluorides
The Disproportionation Pressure of UF3
Reduction of UF4 with Uranium in Alkali Fluorides
Effect of Filter Medium on Stability of UF3
Stability of PbF2-BeF2 Melts in Inconel
Solubility of Metals in Molten Salts
Production of Purified Fluorides
Fuel Purification and Preparation Research
Pilot-Scale Purification Operations
Production-Scale Operations
Batching and Dispensing Operation
Loading and Draining Operations
Special Services
Experimental Preparation of Simple Fluorides
Fundamental Chemistry of Fused Salts
EMF Measurements
Vapor Pressures of LiF-ZrF4 Mixtures
Solubility of Xenon in Fused Salts
X-Ray Diffraction Study of Liquids
High-Temperature X-Ray Spectrometer Studies
51
51
51
52
55
56
59
59
60
60
60
63
64
67
69
71
71
72
72
73
73
75
75
76
76
77
77
80
81
81
81
5. CORROSION RESEARCH
Forced-Circulation Studies
Fluorides in Inconel
Sodium in Inconel
Thermal-Convection Studies
Alkali-Metal Base Mixtures with UF3 and UF4 in Inconel
Zirconium Fluoride Base Mixtures with UF3 and UF4 in Inconel
Effect of Temperature on Mass Transfer
Effect of Loop Size and Shape on Corrosion
Evaluation of Control Loop Results
General Corrosion Studies
Brazing Alloys on Type 310 Stainless Steel and "A" Nickel
in Sodium and in Fuel Mixtures
Screening Tests of Solid-Phase Bonding
Sodium in Inconel
Lithium in Type 347 Stainless Steel
Versene Cleaning of Beryllium-Inconel Systems
Fundamental Corrosion Research
Film Formation on Metals
Mass Transfer and Corrosion in Fused Hydroxide
Chemical Studies of Corrosion
Corrosion of Inconel by LiF-BeF2 and by LiF-BeF2-UF4
83
83
83
86
88
88
90
91
91
93
94
94
96
101
101
102
105
105
110
114
114
Effect of UF3-UF4 Mixtures on Corrosion of Inconel by Various Solvents
Studies of the Sodium Hydroxide-Nickel Reaction
114
115
6. METALLURGY AND CERAMICS
Development of Nickel-Molybdenum Alloys
Fabrication Studies
Oxidation Studies
Stress-Rupture Studies of Nickel-Molybdenum Alloys
Hastelloy B
Modified Nickel-Molybdenum Alloys
Tensile Properties of Hastelloy B
Development of Brazing Alloys
High-Temperature Oxidation Tests
Physical Property Tests
Fabrication of Test Components
Twenty-Tube Heat Exchanger
Intermediate Heat Exchanger No. 2
NaK-to-Air Radiators
Cornell Radiator No. 1
Special Materials Studies
Special Alloy Extrusions
Clad-Columbium Fabrication
B6C-Cu Shielding Material
Magnesium-Lithium Alloy
Welding of Columbium Thermal-Convection Loops
Dimensional Stability Test on an Inconel Spun Core
Brazing of Cermets to Inconel
Ceramic Research
Rare-Earth Ceramics
UO2 Particles Coated with ZrO2
Graphite-Hydrogen Reactions and Erosion Investigation
119
119
119
123
124
124
125
125
128
128
129
129
129
131
134
139
140
140
140
142
143
144
144
145
145
145
147
147
7. HEAT TRANSFER AND PHYSICAL PROPERTIES
Fused Salt Heat Transfer
ART Fuel-to-NaK Heat Exchanger
ART Core Hydrodynamics
Reactor Core Heat Transfer
Free Convection in Fluids Having a Volume Heat Source
Heat Capacity
Viscosity
Thermal Conductivity
Electrical Conductivity
149
149
149
151
154
154
156
157
159
160
8. RADIATION DAMAGE
MTR Static Corrosion Tests
LITR Horizontal-Beam-Hole Fluoride-Fuel Loop
Deposition of 103Ru in LITR Fluoride-Fuel Loop
Miniature In-Pile Loop
Delay of Fission Gases by Charcoal Traps
Creep and Stress-Corrosion Tests
A Theoretical Treatment of 135Xe Poisoning in the ARE and the ART
161
161
163
167
168
169
170
171
9. ANALYTICAL CHEMISTRY OF REACTOR MATERIALS
Determination of Uranium Metal in Fluoride Salt Mixtures
Determination of Trivalent Uranium in Fluoride Fuels
Oxidation of Trivalent Uranium by Methylene Blue
174
174
175
175
Simultaneous Determination of Trivalent Uranium and Total Uranium
176
Determination of Lithium in LiF-BeF2 and LiF-ZrF4-UF4
176
Volumetric Determination of Zirconium in Fluoride Fuels with
Disodium Dihydrogen Ethylenediaminetetraacetate
177
Determination of Oxygen in Fluoride Fuels
178
Determination of Oxygen in Metallic Oxides by Bromination
178
Determination of Oxygen in Beryllium Oxide by Acidimetry
179
Determination of Trace Amounts of Nickel in Fluoride Fuels with Sodium Diethyldithiocarbamate 179
ANP Service Laboratory
180
10. RECOVERY AND REPROCESSING OF REACTOR FUEL
Pilot Plant Design
Process Development
Corrosion Studies
181
181
181
182
PART III. SHIELDING RESEARCH
11. SHIELDING ANALYSIS
Gamma-Ray Distribution in a Circulating-Fuel Reactor and Shield
Energy Absorption Resulting from Gamma Radiation Incident on a
Multiregion Shield with Slab Geometry
Energy and Angular Distribution of Air-Scattered Neutrons from a Monoenergetic Source
Analysis of the Constant-Velocity Transport Equation
191
191
12. LID TANK SHIELDING FACILITY
Reflector-Moderated Reactor and Shield Mockup Tests
Gamma-Ray Dose Rate Measurements
Neutron Measurements
Sodium Activation in Heat Exchanger Region
194
194
194
197
198
13. BULK SHIELDING FACILITY
GE-ANP Air-Duct Mockup Experiment
The Spectrum of Fission-Product Gamma Rays
200
200
203
14. TOWER SHIELDING FACILITY
The Differential Shielding Experiments at the TSF: Phase I
Measurements in the Detector Tank
Measurements in the GE-ANP Crew Compartment
Analysis of the Differential Shielding Experiments
Definition of Dose Scattering Probability
Evaluation of Probability from TSF Experiments
Evaluation of Direct-Beam Integral
Calculation of Scattered Dose
Effects of Direct-Beam Collimation
Effect of Neutron Energy Spectrum
Application of the Differential Shielding Experiments
205
205
205
205
206
208
213
214
215
216
216
217
192
192
193
PART IV. APPENDIX
15. LIST OF REPORTS ISSUED FROM FEBRUARY 1955 THROUGH MAY 11, 1955
227
ORGANIZATION CHARTS
231
ORNL-1947
AIRCRAFT NUCLEAR PROPULSION PROJECT
QUARTERLY PROGRESS REPORT
For Period Ending September 10, 1955
FOREWORD
SUMMARY
PART I. REACTOR THEORY, COMPONENT DEVELOPMENT, AND CONSTRUCTION
1. REFLECTOR-MODERATED REACTOR
Aircraft Reactor Test Facility
Shielding Experiment Facility
Aircraft Reactor Test Design
Reactor Design
Main and Auxiliary Radiator Design
Fuel-to-NaK Heat Exchanger Design
Core Flow Studies
Core Design Analyses
Fuel Pump Performance
Controls and Instrumentation
Engineering Test Unit
Reactor Physics
Control Rod Heating and Burnup
ART Boron Layer
High-Temperature Critical Experiment vs ART
Multigroup, Multiregion Reactor Calculation
15
15
15
15
15
19
19
24
28
29
30
31
33
33
33
33
35
2. EXPERIMENTAL REACTOR ENGINEERING
In-Pile Loop Development and Tests
Loop Installation
Loop No. 1 Operation
Horizontal-Shaft Sump Pump
Oil Irradiation
Development and Operation of Forced-Circulation Corrosion and Mass Transfer Tests
Operation of Fused Salt-Inconel Loops
Liquid Metals in Multimetal Loops
Pump Development
Mechanical Shakedown and Bearing-and-Seal Tests
Short-Circuit Pump-Test Stand
High-Temperature Pump-Performance Test Stand
Heat Exchanger Tests
Intermediate Heat Exchanger Tests
Small Heat Exchanger Tests
Structural Tests
Outer Core Shell Thermal Stability Test
Inconel Strain-Cycling Tests
Thermal-Cycling Test of Sodium-Inconel-Beryllium System
Cold Traps and Plug Indicators
36
36
36
36
37
38
38
38
38
42
42
44
44
45
45
49
51
51
52
54
54
3. CRITICAL EXPERIMENTS
Room-Temperature Reflector-Moderated-Reactor Critical Experiments
High-Temperature Reflector-Moderated-Reactor Critical Experiments
58
58
58
PART II. MATERIALS RESEARCH
4. CHEMISTRY OF REACTOR MATERIALS
Phase Equilibrium Studies of Systems Containing ZrF4 and/or UF4
The System LiF-ZrF
The System UF4-ZrF4
The System NaF-LiF-ZrF4
The System NaF-LiF-UF4
The System NaF-RbF-ZrF4-UF4
The System KF-ZrF4
The System NaF-KF-ZrF4
Phase Equilibrium Studies of Systems Containing BeF2
The System NaF-LiF-BeF2
The System NaF-LiF-BeF2-UF4
The System NaF-BeF2-UF4
The System KF-BeF2
The System NaF-KF-BeF2
Solubility of UF3 in BeF2-Bearing Compositions
Chemical Reactions in Molten Salts
Equilibrium Reduction of FeF2 by H2 in NaZrF5
Reduction of UF4 by Structural Metals
Stability of Chromium and Iron Fluorides in Various Molten Fluorides
Experimental Preparation of Pure Fluorides
Reaction of UF4 with Uranium in Alkali Fluorides
Reaction of Uranium Metal with Alkali Fluoride Mixtures
Metal-Salt Equilibrium
Production of Purified Fluorides
Recovery of Contaminated Fuel for Re-use
Removal of CrF2 from NaF-ZrF4-UF4 Mixtures
Effect of ZrO2 in Fuel Preparation
Pilot-Scale Purification Operations
Production-Scale Operations
Preparation of ZrF4
Batching and Dispensing Operations
Loading and Draining Operations
Enriched Fuel Preparations
Fundamental Chemistry of Fused Salts
Solubility of Xenon in Molten Salts
EMF Measurements in Fused Salts
Activity of Chromium in Inconel
Viscosities of Molten Nitrates
Optical Properties and X-Ray Patterns for Recently Discovered
Compounds in Fluoride Systems
High-Temperature X-Ray Spectrometer Studies
Physical Chemistry of Fused Salts
Diffraction Studies of Liquids
65
65
65
67
67
67
68
69
69
69
69
70
70
71
71
72
72
72
73
74
78
78
79
79
81
81
81
82
83
83
83
84
84
84
85
85
85
87
88
5. CORROSION RE5EARCH
Forced-Circulation Studies
Fluorides in Inconel
Sodium in Inconel and in Stainless Steel
Thermal-Convection Studies
95
95
95
97
100
88
93
93
94
Effect of Various Loop Cleaning Methods
Effect of Heating Method
Effect of Temperatures
Effect of Applied Electromotive Forces
Effect of Oxide Additions to Sodium
General Corrosion Studies
Hot-Pressed Metal Bonded Tungsten Carbide in NaF-ZrF4-UF4
Solid-Phase Bonding of Cermets
Effects of Ruthenium on Physical Properties of Inconel
Brazing Alloys on Inconel and on Nickel in Sodium and in NaF-ZrF4-UF4
Brazing Alloys on Inconel and on Stainless Steel in Lithium
Hastelloy B-Inconel in NaF-ZrF4-UF4
Boiling Sodium in Inconel
Inconel Exposed to a Sodium-Potassium-Lithium Mixture
Molybdenum, Vanadium, and Niobium in Static Lithium
Analysis of Metal Crystals from Inconel-Sodium Thermal-Convection Loop
Fundamental Corrosion Research
Film Formation on Metals
High-Temperature Spectrophotometry in Fused Hydroxides
Mass Transfer and Corrosion in Fused Hydroxides
Thermal Dissociation of Sodium Hydroxide
Chemical Studies of Corrosion
Inconel in NaF-LiF-ZF4-UF4
Stability of UF3 in NaF-KF-LiF in Inconel
Effect of Chromium on the Mass Transfer of Nickel in NaOH
6. METALLURGY AND CERAMICS
Mechanical Property Tests of Inconel
Stress-Rupture Tests
Bellows Test
Interaction Between Inconel and Beryllium
Development of Nickel-Molybdenum Alloys
Oxidation Studies
Fabrication Studies
Stress-Rupture Tests of Hastelloy B
Physical Properties and Microstructure Studies of Hastelloy B
Brazing Alloy and Testing
Development Tests
Brazing of Boron Carbide
Brazing of Cermet Valve Seats to Inconel Components
Fabrication of Test Components
Components for High-Temperature Critical Experiment
NaK-to-Air Radiator
Intermediate Heat Exchanger No. 3
Cornell Radiator No. 2
Nondestructive Testing
Ceramic Research
Graphite-Hydrogen Corrosion-Erosion Investigation
Rare-Earth-Oxide Control Rods
Calcium Fluoride and Alumina Detector Spacers
Fluoride Fuel Pellets
Synthesis of Boron Compounds
Fabrication of Dysprosium Oxide Disks
Fabrication of Europium Oxide Wafers
Special Materials Studies
Columbium Research
100
101
101
102
102
104
104
104
106
106
108
109
109
111
111
113
113
113
117
117
118
119
119
120
120
122
122
122
123
124
125
125
126
127
127
130
130
130
131
132
132
133
134
135
136
140
140
140
140
140
140
143
143
144
144
Composite Tubing Fabrication
Oxidation Tests of Aluminum Bronze
Lead-Calcium Alloys
Neutron Shielding Material
145
146
146
147
7. HEAT TRANSFER AND PHYSICAL PROPERTIES
Fused Salt Heat Transfer
ART Fuel-to-NaK Heat Exchanger
ART Core Hydrodynamics
Reactor Core Heat Transfer
Heat Capacity
Viscosity
Thermal Conductivity
Electrical Conductivity
149
149
150
151
151
154
155
157
157
8. RADIATION DAMAGE
LITR Horizontal-Beam-Hole Fluoride-Fuel Loop
Miniature In-Pile Loop
Creep and Stress-Corrosion Tests
Flux Measurements in the MTR
Analysis of Reactor-Grade Beryllium
158
158
164
165
166
169
9. ANALYTICAL CHEMISTRY OF REACTOR MATERIALS
Determination of Oxygen in Sodium
n-Butyl Bromide Method
Vacuum-Distillation Method
Volumetric Determination of Zirconium in Fluoride Salts with
Disodium Dihydrogen Ethylenediaminetetraacetate (EDTA)
Determination of Uranium Metal in Fluoride Salt Mixtures
Elimination of Air from a Dry Box
Determination of Oxygen in Metallic Oxides by Bromination
Determination of CO by Means of a Solution of PdCl2
ANP Service Laboratory
172
172
172
173
10. RECOVERY AND REPROCESSING OF REACTOR FUEL
Pilot Plant Design
Engineering Developments
Process Development
179
179
179
180
173
175
175
175
176
177
PART III. SHIELDING RESEARCH
11. SHIELD DESIGN
Weights of Spherically Symmetric Unit Shields for Circulating-Fuel Reactors
Sources of Radiation in a 300-MW Circulating-Fuel Reactor
Shield Weight Dependence on the Dimensions of a 300-MW Circulating-Fuel Reactor
Neutron Shield
Gamma-Ray Shield
Weight Determinations
185
185
185
189
190
191
195
12. LID TANK SHIELDING FACILITY
Reflector-Moderated-Reactor and Shield Mockup Tests
Gamma-Ray and Neutron Measurements Beyond the Mockups
Sodium Activation in the Heat Exchanger Region of the Mockups
197
197
197
197
13. BULK SHIELDING FACILITY
Angular Distribution of Fast Neutrons Through Water
Decay of Fission-Product Gamma Radiation
199
199
201
14. TOWER SHIELDING FACILITY
Procedure for Using TSF Data for the Optimization of a Divided Neutron Shield
Calculation of Shield Weight
Calculation of Dose Rate
Calculation of Minimum Shield Weight for Specified Dose
Application of TSF Data
Results of a Sample Shield Optimization Calculation
Measurements in the GE-ANP Crew-Compartment Mockup
205
205
205
206
208
211
215
217
ORGANIZATION CHARTS
221
ORNL-2157
AIRCRAFT NUCLEAR PROPULSION PROJECT
QUARTERLY PROGRESS REPORT
For Period Ending September 10, 1956
FOREWORD
vii
SUMMARY
1
PART 1. AIRCRAFT REACTOR ENGINEERING
1.1. AIRCRAFT REACTOR TEST DESIGN
Status of ART Design
Reactor Assembly
Reflector-Moderator Cooling Circuit
Heat Exchangers
Fuel Pumps and Expansion Tank
Fuel Recovery Tank
Applied Mechanics and Stress Analysis
Reactor Support
NaK Piping Inside Reactor Cell
Fill-and-Drain Tank and Support
Core-Shell Low-Frequency Thermal-Cycling Test
Core Hydrodynamics
17
17
17
17
17
17
17
18
18
18
21
23
26
1.2. ART PHYSICS
Comparison of Basic Gamma-Ray Data with Bulk Shielding Reactor
Gamma Heating Measurements
Gamma-Ray Heating in ART
Gamma-Ray Source Strength
Gamma-Ray Heating
29
1.3. ART INSTRUMENTS AND CONTROLS
Reflector-Moderator Temperature Control Simulation
Instrument Development
Fuel-Expansion-Tank Level Indicator
Systems for Testing Liquid-Level-Sensing Devices in Flowing Liquids
High-Temperature Turbine-Type Flowmeter
High-Temperature Pressure Transmitter
Tests of Heliarc-Welded Inconel-Sheathed Thermocouples in Sodium
Thermocouple Data Reduction
35
35
35
35
36
36
37
37
37
1.4. COMPONENT DEVELOPMENT AND TESTING
Pump Development Tests
Bearing and Seal Tests
Test of Gas Attenuation by Seals
Fuel Pump Development Tests
Fuel Pump Endurance Tests
Sodium Pump Development Tests
Primary and Auxiliary NaK Pump Development Tests
Heat Exchanger and Radiator Development Tests
Intermediate Heat Exchanger Tests
39
39
39
39
40
42
43
43
43
43
29
31
31
32
Small Heat Exchanger Tests
Cold-Trap Evaluation in Heat Exchanger Test Loops
Water Flow Tests of Aluminum North-Head Mockup
Dump Valve Development Tests
Outer Core Shell Thermal Stability Test
Auxiliary Component Development
High-Frequency Thermal-Cycling Apparatus
Cold Traps and Plugging Indicators
Liquid-Metal-Vapor Condensers
Zirconium Fluoride Vapor Trap
47
51
52
53
55
56
56
57
60
61
1.5 PROCUREMENT AND CONSTRUCTION
ART Facility
ART-ETU Reactor Construction
ETU Facility
ART-ETU Reactor Fabrication and Assembly
ART Cell Components
ART-ETU Reactor Component Procurement
Fuel-to-NaK Heat Exchangers
Sodium-to-NaK Heat Exchangers
Core Shells
Beryllium Reflector-Moderator
Boron Layers
Pressure Shell
Inconel
64
64
78
78
78
79
79
79
79
79
80
80
80
80
1.6 IN-PILE LOOP DEVELOPMENT AND TESTS
Operation of In-Pile Loop No. 5
In-Pile Loop No. 6
Horizontal-Shaft Sump Pump for In-Pile Loops
81
81
81
81
1.7 ADVANCED REACTOR DESIGN
Graphite and Beryllium Oxide Moderated Circulating-Fluoride-Fuel Reactor
Hydride-Moderated Circulating-Fuel Reactor
82
82
84
PART 2. CHEMISTRY
2.1 PHASE EQUILIBRIUM STUDIES
The System LiF-RbF
The System LiF-UF4
The System RbF-UF4
The System NaF-RbF-UF4
The System NaF.RbF-ZrF4-UF4
The System RbF-CaF2
The Alkali Fluoride-Cerous Fluoride Systems
The System CsF-BeF2
The System NaF-LiF-BeF2
The System NaF-RbF-BeF2
The System KCl-ZrCl4
87
87
87
88
90
91
91
92
92
93
94
94
2.2 CHEMICAL REACTIONS IN MOLTEN SALTS
Equilibrium Reduction of NiF2 by H2 in NaF-ZrF4
Stability of NiF2 in NaF-ZrF4 Mixtures
Activity of Chromium in Chromium-Nickel Alloys
Solubility and Stability of Structural Metal Fluorides in Various Fluoride Mixtures
Reduction of UF4 by Structural Metals
96
96
97
100
100
103
Solubility Determinations by Measurement of Electromotive Forces of Concentration Cells
Activities in the RbF-ZrF4 System
Activities in the KF-ZrF4 System
Solubility of LaF3 and of CeF3 in Molten Fluoride Mixtures
Solubility of Xenon in Fused Salts
Molten Salt Polarography
Activities from EMF Measurements on Solid Solutions of Salts
106
108
109
110
113
113
116
2.3 PHYSICAL PROPERTIES OF MOLTEN MATERIALS
Surface Tension and Density of NaF-ZrF4 Mixtures
Surface Tensions of Molten Salts
Fluorozirconate Mixtures
Uranium Tetrafluoride
118
118
118
118
119
2.4 PRODUCTION OF PURIFIED FLUORIDE MIXTURES
Laboratory-Scale Purification Operations
Quality Control of Raw Materials and Products
Pilot-Scale Purification Operations
Production-Scale Operations
Batching and Dispensing Operations
Preparation of ZrF4 from ZrCl4
Special Services
Filling, Draining, and Sampling Operations
Special Enriched Fuel for In-Pile Loops
Shield Mockup Core Materials
Experimental Preparation of Various Fluorides
120
120
120
120
120
121
121
121
121
122
122
122
2.5 COMPATIBILITY OF MATERIALS. AT HIGH TEMPERATURES
Penetration of Graphite by Molten Fluorides
Hydrogen Pressure of the NaOH-Ni Reaction
Physical Properties of Elastomers Exposed to Attack by Liquid Metals
Determination of Oxygen in NaK
123
123
123
124
124
2.6 ANALYTICAL CHEMISTRY
Determination of Rare-Earth Elements in Fluoride Fuels
Spectrophotometric Determination of Cerium
Spectrophotometric Determination of Lanthanum
Determination of Tantalum in Fluoride Salts
Determination of Oxygen in NaK
Sampler for Alkali Metals
Determination of Oxygen, Nitrogen, and Carbon in Metallic Lithium
Determination of Oxygen
Determination of Nitrogen and Carbon
Detection of Traces of NaK in Air
Compatibility of Fluoride Salts and Alkali Metals with Pump Lubricants
Extraction of ART Fuel Components with Trioctylphosphine Oxide
Determination of Chromium in Trioctylphosphine Oxide Extracts with Diphenyl Carbazide
ANP Service Laboratory
125
125
125
125
125
126
126
127
127
128
129
129
131
131
132
PART 3. METALLURGY
3.1 DYNAMIC CORROSION
Forced-Circulation Loop Tests
Fuel Mixtures in Inconel and Hastelloy B
Sodium in Inconel and Stainless Steel
Sodium-Beryllium-lnconel Compatibility
135
135
135
138
139
Thermal-Convection Loop Tests
Sodium-Beryllium-Hastelloy B Compatibility
Sodium-Beryllium-lnconel Compatibility
Fuel Mixtures in Hastelloy and Special Nickel-Molybdenum Alloy Loops
Special NaF-ZrF4-UF4 Mixtures in Inconel Loops
Screening Tests of Special Fuel Mixtures
Inconel Strain-Cycling Tests
139
139
141
141
143
145
147
3.2 GENERAL CORROSION STUDIES
Tests of Inconel Tube-to-Header Joints with Recrystallized Welds in NaK and in Fluoride Fuel
Tests of Coast Metals Brazing Alloy No. 53 in NaK and in Fluoride Fuel
Tests of Haynes Brazing Alloy No. 40 in NaK and in Fluoride Fuel
Niobium in Sodium and in Lithium
Vapor-Zone Attack in Inconel-Fluoride Fuel Systems
Carburization of Various Alloys by Molten Sodium
Sodium-Beryllium-Inconel Compatibility in a Static System (Test No. 2)
Effect of Diffusion Cold Traps on Mass Transfer in lnconel-Sodium Thermal-Convection Loops
Thermal-Convection Loop Tests of Various Structural Materials and Lithium
Tests of Intermetallic Compounds in Sodium and in Fluoride Fuel
149
149
152
153
154
156
156
160
161
163
169
3.3 FABRICATION RESEARCH
Nickel-Molybdenum Alloy Development
Battelle Memorial Institute Alloys
International Nickel Company Alloys
ORNL Alloys
Hastelloy W Seamless Tubing
Consumable-Electrode Experiments
Shield Plug for ART Pumps
Gamma-Ray Shielding Material
Thermal Shield
Neutron Shield Material for the ART
Ceramic B4C Tiles
Clad Copper-B4C Cermets
Lithium-Magnesium Alloys
Tubular Control Rods
Seamless Tubular Fuel Elements
Niobium Fabrication Studies
Evaluation of Arc-Melted Niobium
Nb-UO2 Compacts
Nb-U Alloys
Fabrication of Hydrides
173
173
173
176
176
177
177
177
177
180
180
180
180
180
181
182
183
183
183
183
183
3.4 WELDING AND BRAZING INVESTIGATIONS
Fabrication of Primary NaK Pump Volutes
Fabrication of Primary NaK Pump Impellers
Shrinkage of Inconel Core Shell Welds
Examinations of NaK-to-Air Radiators After Service
Fabrication of Cermet Valve Components
Continuous Production of Sintered Brazing Alloy Rings
Fabrication of Heat Exchangers and Radiators
Studies of the Aging Characteristics of Hastelloy B
184
184
192
192
195
197
200
201
202
3.5 MECHANICAL PROPERTIES STUDIES
Relaxation Testing of Inconel
Effects of Fused-Salt Corrosion on the Stress-Rupture Properties of Hastelloy X
Creep-Rupture Testing of an 80% Mg-20% Li Alloy
205
205
206
208
3.6. CERAMIC RESEARCH
Rare-Earth Materials
Fuel and Moderating Materials
Component Fabrication
High-Temperature X-Ray Diffraction
Fluoride Fuel investigations
211
211
211
211
211
211
3.7. NONDESTRUCTIVE TESTING STUDIES
Eddy-Current Inspection of Small-Diameter Tubing
Inspection of Tubing by the Ultrasonic Method
Inspection of Pipe
Inspection of Thin Sheet
212
212
212
217
218
3.8. INSPECTION OF MATERIALS AND COMPONENTS
Weld Inspections
Material Inspections
Inspection of Components
Fluorescent-Penetrant Inspection of Tubing
Welder Qualification Program
220
220
220
221
221
221
PART 4. HEAT TRANSFER AND PHYSICAL PROPERTIES, RADIATION DAMAGE,
FUEL RECOVERY AND REPROCESSING, CRITICAL EXPERIMENTS
4.1 HEAT TRANSFER AND PHYSICAL PROPERTIES
ART Fuel-to-NaK Heat Exchanger
ART Hydrodynamics
Core Hydrodynamics
Sodium Flow in Reflector Cooling System
Fluid Flow Visualization
ART Core Heat Transfer Study
Thermal-Cycling Experiment
Shield Mockup Core Study
Heat Capacity
Viscosity and Density
Thermal Conductivity
225
225
225
225
226
227
227
228
233
233
233
234
4.2 RADIATION DAMAGE
Examination of Disassembled MTR In-Pile Loops Nos. 3, 4, and 5
Investigation of Materials Removed from MTR In-Pile Loops Nos. 3 and 5
Creep and Stress-Corrosion Tests of Inconel
MTR Stress-Corrosion Apparatus
Effect of Radiation on Static Corrosion of Structural Materials by Fused Salt Fuels
Holdup of Fission Gases by Charcoal Traps
ART Off-Gas System Instrumentation Analysis
LITR Vertical In-Pile Loop
Design Calculations for LITR Vertical In-Pile Loop
ART Reactivity Transients Associated with Fluctuations in Xenon-Removal Efficiency
Use of Zr95 as a Fission Monitor
Fast-Neutron Detectors
Effects of Radiation on Electronic Components
Irradiation Effects on Thermal-Neutron Shield Materials
Irradiations of Stressed Shielding Materials
236
236
239
240
243
243
245
245
245
248
250
252
252
254
256
258
4.3 FUEL RECOVERY AND REPROCESSING
Volatility Pilot Plant Design and Construction
261
261
Engineering Development
Chemical Development
261
262
4.4 CRITICAL EXPERIMENTS
Reflector-Moderated Reactor Experiments
Experiments at Room Temperature
Experiments at Elevated Temperature
264
264
264
264
PART 5. REACTOR SHIELDING
5.1 SHIELDING THEORY
A Monte Carlo Study of the Gamma-Ray Energy Flux, Dose Rate, and Buildup
Factors in a Lead-Water Slab Shield of Finite Thickness
271
5.2 LID TANK SHIELDING FACILITY
Study of Advanced Shielding Materials
278
278
5.3 BULK SHIELDING FACILITY
The Fission-Product Gamma-Ray Energy Spectrum
Gamma-Ray Streaming Through the NaK Pipes that Penetrate the ART Shield
291
291
296
5.4 SHIELD MOCKUP CORE
Selection of Calculational Models
Calculational Procedure
Calculations for SMC Configurations Using UO2-Stainless Steel Fuel Elements
Calculations for SMC Configurations Using Uranium-Aluminum Fuel Elements
Core Gamma Rays
Neutron-Capture Gamma Rays from the Core Shells
Neutron-Capture Gamma Rays from the Reflector
Gamma Rays from the Heat Exchanger Region
Neutron-Capture Gamma Rays from the Pressure Shell and Shield
Neutron-Capture Gamma Rays from the Air and Crew Compartment
Design Status
299
299
301
301
305
309
310
310
310
310
310
310
271
ORNL-2387
AIRCRAFT NUCLEAR PROPULSION PROJECT
QUARTERLY PROGRESS REPORT
For Period Ending September 30, 1957
FOREWORD
vii
SUMMARY
xvii
PART 1. AIRCRAFT REACTOR ENGINEERING
1.1 REACTOR AND FACILITY CONSTRUCTION
Methods Development
Weld Tests
Equipment Inspection
Component Fabrication and Assembly
Main Fuel-to-NaK Heat Exchanger
Sodium-to-NaK Heat Exchangers
ART-ETU Radiators
Main Pressure Shell and Liner
Beryllium Reflector-Moderator Outer Shell
Boron Shield Containers - Shells IV and V
Inner and Outer Core Shells
Reactor North Head
Strut Load Ring
Neutron Shielding
Lead and Tungsten Shielding
Miscellaneous Components
Reactor Assembly
ETU Facility
Reactor Support Structure
NaK Piping, Associated Supports, and Components
Electrical Equipment
Auxiliary Services
ART Facility
Design Activity
Construction Progress
Installation Planning
ART Disassembly
Reactor Disassembly
Cutting Methods Evaluation
Facility Investigations
3
3
3
4
5
5
5
5
9
9
9
13
13
15
16
18
19
21
22
22
22
25
25
25
25
27
27
31
31
31
31
1.2 COMPONENT DEVELOPMENT AND TESTING
Pump Development Tests
Bearing, Seal, and Lubricant Tests
Aluminum North Head Water Tests
Fuel Pump High-Temperature-Performance Tests
Fuel Pump Endurance Tests
Primary and Auxiliary NaK Pump Development
Reactor Component Development Tests
Heat Exchanger and Radiator Development Tests
32
32
32
32
34
35
35
38
38
Valve Development Tests
Sodium Circuit Water Flow Tests
Outer Core Shell Thermal Stability Test
Liquid-Metal-Vapor Condensers
Zirconium Fluoride Vapor Traps
Island Bellows Test
Fuel Fill-and-Drain Tank Test
43
44
45
46
48
48
52
1.3 INSTRUMENT AND CONTROLS DEVELOPMENT
ART Control Rod Drive Test
Fuel-Expansion-Tank Liquid-Level Indicator
Bubbler Plugging Tests
Aluminum North Head Expansion Tank Tests
On-Off Level Probes
Magnetic Flowmeters
Liquid-Metal-Level Transducers
ART Thermocouples
Sheathed Thermocouples
Well Thermocouples
Surface Thermocouples
Apparatus for Checking Thermocouples
54
54
54
54
55
58
58
59
61
61
66
68
71
1.4 ENGINEERING DESIGN STUDIES
Applied Mechanics and Stress Analysis
Thermal Stress Cycling Tests of Beryllium
Thermal-Cycling Tests of a Welded Core Shell Model
Stress Analysis of Island Bellows
Stress Analysis of Shield Support Structure
Stress Analysis of a Pressure-Measuring Instrument
Apparatus for ETR In-Pile Tests of Moderator Materials
72
72
72
73
73
75
77
78
1.5 DESIGN PHYSICS
ART Fill-and-Drain Tank Shielding
Penetrations
Overlap in Shield at Removable Top Section
Incompleted Work
Dose Rate in Region of ART Pumps
Decay of Gamma Activity in U235-Containing ART Fuel for Short Times After Shutdown
Decay-Gamma Heating in ART Fuel Drain Valves
80
80
80
81
81
81
82
82
1.6 MATERIALS AND COMPONENTS INSPECTION
Material Inspection
Tubing
Pipe, Plate, Sheet, Rod, and Fittings
Embrittlement of Inconel by Penetrants
Chemical Analyses of Materials
Electrical Calrods
Weld Inspection
Inspection of Reactor Shells
Inner Core Shells (Shell I)
Outer Core Shells (Shell II)
Shell III
Shells IV and V
Inspection of Components Received from Vendors
York Corp. Radiators and Radiator Materials
Griscom-Russell Co. Heat Exchangers
83
83
83
83
84
84
84
84
86
86
86
86
86
87
87
87
Black, Sivalls & Bryson Heat Exchangers
Midwest Piping Company Forgings and Weldments
Process Engineering, Inc., Tanks and Bellows Expansion Joints
Fulton-Sylphon Company Bellows
Hoke, Inc., Inconel and Stainless Steel Valves
Metal Identification Meter
Instrumentation and Controls Inspections
Nickel-Copper Welds in Liquid-Level Probes
Thermocouple Welds
Procedures for Radiographic Inspection of Weldments on ART Island and Reflector
1.7 HEAT TRANSFER STUDIES
Thermal-Cycling Research
Pressurized System
Pulse-Pump System
Thermocouple Development
ART Hydrodynamics
Full-Scale Core Studies
Quarter-Scale Core Studies
Instantaneous Velocity Profile Measurements
Fused Salt Heat Transfer
Heat Transfer Experiments
ART-Type Core with Screens
Vortex Tube
Liquid-Metal Volume-Heat-Source Experiment
Mass Transfer
Physical Properties
Enthalpy and Heat Capacity
Thermal Conductivity
Properties of Zirconium Fluoride Vapor Deposits
88
88
88
88
88
88
89
89
89
90
91
91
91
93
96
96
96
98
103
103
104
104
105
106
106
108
108
108
109
PART 2. CHEMISTRY
2.1 PHASE EQUILIBRIUM STUDIES
The System KF-UF4
The System NaF-HfF4
The System KBF4-NaBF4
Yttrium Fluoride Systems
113
113
114
114
114
2.2 CHEMICAL REACTIONS IN MOLTEN SALTS
Equilibrium Reduction of NiF2 by H2 in NaF-ZrF4
Activity Coefficients of NiF2 in Molten NaF-ZrF4 Solutions
Thermodynamic Considerations Relating to the Activity of NiF2
Reduction of UF4 by Structural Metals
Stability of Chromium Fluorides in NaF-LiF-KF
Reduction of FeF2 by Cr° in RbF-ZrF4
Solubility of Structural Metal Fluorides in RbF-ZrF4
Activities in Alloys
Emf Measurements in Molten Salts
Daniell Cells in Fluoride Melts
Emf Measurements of Chloride Melts
Solubility of Helium, Argon, and Xenon Gases in NaF-ZrF4
Solubility of HF in NaF-ZrF4-Mixtures
Solubility of HF in NaF-KF-LiF Mixtures
Solubility of CeF3 as a Function of Solvent Composition
Precipitation of Cerium as Ce2O3 from Molten LiF-KF Eutectic
117
117
117
121
124
125
126
128
130
131
131
132
134
136
137
138
139
Stability of UO2F2 in Fused Salts
Oxidation of Mixtures Composed of Sodium and Potassium
141
142
2.3 PHYSICAL PROPERTIES OF MOLTEN MATERIALS
Vapor Pressure of HfF4
Vapor Pressure of BeF2
144
144
144
2.4 PRODUCTION OF PURIFIED MIXTURES
Preparation of Various Special Fluorides
Preparation of YF3
Preparation of Other Fluorides
Production and Dispensing of Fused Salts and Liquid Metals
Experimental Batch Production
Dispensing and Servicing Operations
Materials Available
146
146
146
146
146
146
147
147
2.5 ANALYTICAL CHEMISTRY
Determination of Traces of NaK in Air
Determination of Oxygen in Metallic Lithium
Determination of Oxygen in Fluoride Salts and in Metals
Determination of Nickel in Metallic Sodium
Formation of Carbides by the Reaction of Pump Lubricants and NaK at Elevated Temperatures
Determination of Aluminum in Mixtures of Fluoride Salts
Solvent Extraction of Titanium and Niobium from Acidic Solutions with
Tri-n-octylphosphine Oxide
Extraction of Sulfuric Acid
Extraction of Titanium
Extraction of Niobium
Installation of a Microbalance in a Vacuum Drybox
148
148
149
150
152
154
156
156
156
156
157
157
PART 3. METALLURGY
3.1 NICKEL-MOLYBDENUM ALLOY DEVELOPMENT STUDIES
Material Development
Properties of INOR-8
Properties of INOR-9
Studies at University of Tennessee
Studies at Battelle Memorial Institute
Studies of Stress-Rupture Properties at New England Materials Laboratory
INOR-8 Alloys Produced by Superior Tube Company
Status of Production Heats
Composite Tubing
Joining Experimental INOR-8 Alloys
Stress-Rupture Properties of Nickel-Molybdenum Base Alloys in a Fuel Environment
Corrosion Studies
Forced-Circulation Loop Test of a Nickel-Molybdenum Base Alloy Exposed to Fuel 107
Thermal-Convection Loop Tests of Nickel-Molybdenum Base Alloys
Exposed to Fuel 107
Compatibility of Nickel-Molybdenum Base Alloys with Molybdenum
161
161
162
162
163
163
163
163
164
167
168
171
176
176
3.2 DEVELOPMENT STUDIES OF INCONEL
Strain-Cycling and Stress-Relaxation Studies
Biaxial Creep Studies
Relative Tensile Properties of Inconel Plate and Inconel Weld Deposits
Brazing Alloys for Inconel Joints
Oxidation Studies
182
182
185
192
196
196
179
181
Corrosion Studies
Effect-of Grain Size on Corrosion of Inconel by Fuel 30
196
199
3.3 WELDING AND BRAZING STUDIES
Examination of All-Welded Inconel Impeller That Cracked in Service
Brazed-Joint Cracking Tests
Fabrication of ART Fuel Fill-and-Drain Tanks
Correlation of Radiographic and Metallographic Determinations
of Porosity in Tube-to-Header Welds
Fabrication of Sodium-to-NaK Heat Exchangers
Investigation of Material for Radiator Headers
Fabrication of a Small Semicircular, Heat-Exchanger
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3.4 CORROSION AND MASS TRANSFER STUDIES
Corrosion of Vanadium in Fluoride Fuel and in Lithium
Molybdenum and Niobium in Contact with Lithium
Tungsten-Nickel-Copper Alloy in Sodium
Tungsten Carbide- and Titanium Carbide-Base Cermets in Sodium
Experimental Studies with Molten Lithium
Inert Atmosphere Chamber for Thermal-Convection Loop Testing of
Nonoxidation-Resistant Materials
Forced-Circulation Loop Tests of Sodium in Hastelloys, Inconel and Stainless Steel
Diffusion of Nickel in Liquid Lead
Purification of Sodium
Mass Transfer in Aqueous Solutions
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3.5 MATERIALS FABRICATION RESEARCH
Yttrium Metal Production
Hydrogen Diffusion Through Metals
Volatility of BeO in Steam at Moderator Temperatures
Fabrication of High-Density BeO
BeO Thermocouple Inserts and Irradiation Test Specimens
Thermal Stress Resistance of Ceramic Cylinders
Fabrication of Metal Hydrides
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3.6. METALLOGRAPHIC EXAMINATIONS OF ENGINEERING TEST COMPONENTS
AFTER SERVICE
ART Prototype Test Radiator
York Corp. Radiator No. 16
Process Engineering Corp. Heat Exchanger No. 3, Type SHE-7
Process Engineering Corp. Heat Exchanger No. 2, Type SHE-7
Inconel Centrifugal Pump That Circulated NaK
Welds of Test Components
Thermal-Convection Loop Welds
Forced-Circulation Loop Welds
Heat Exchanger Welds
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3.7 NONDESTRUCTIVE TESTING
Eddy-Current Measurements of Metal Thickness
Mathematical Analysis of Eddy-Current Probe Coils
Inspection of Tubing
Inspection of Pipe
Plate Inspection
Core Shell Inspection
The Detection of Unbonded Areas in Plates with Resonance Ultrasound
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PART 4. RADIATION DAMAGE
4.1 RADIATION DAMAGE
Examination of Irradiated Components and Materials
MTR In-Pile Loops
Moderator Materials
ARE Specimens
Creep and Stress-Rupture Tests of Inconel
MTR Experiments
LITR Experiments
LITR Vertical In-Pile Loop
MTR Static Corrosion Tests
Flux Monitoring of MTR Static Corrosion Capsules
Relative Contribution from the 60Ni(n,p)60Co Reaction to the 60Co
Disintegration Rate in Irradiated Inconel
ETR Irradiation of Moderator Materials
Effect of Irradiation on Thermal-Neutron Shield Materials
Boron Nitride
Boron Carbide
Cermets
Effects of Radiation on Electronic Components
Experimental Results
Experimental Refinements
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PART 5. REACTOR SHIELDING
5.1 LID TANK SHIELDING FACILITY
Radiation Attenuation Measurements in Plain Water, Borated Water, and Oil
Study of Advanced Shielding Materials
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5.2 BULK SHIELDING FACILITY
The Suppression of Capture Gamma Rays by Lithium in Lead
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5.3 TOWER SHIELDING REACTOR-II
Mechanical Design
Nuclear Calculations
Fuel Element Development
Development of the Control Device
Calculation of the Gamma-Ray Heating in the Lead Shield
Heating at the Core-Shield Interface
Heating Within the Shield
Conclusions
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5.4 SHIELD DESIGN
Monte Carlo Calculation of Gamma-Ray Penetration of Aluminum Slabs
Monte Carlo Calculation of the Gamma-Ray Penetration of Lead-Water Slabs
Monte Carlo Calculation of Gamma-Ray Dose Rate Buildup Factors for Lead and Water Shields
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