Advanced Nuclear Energy Systems:
Heat Transfer Issues and Trends
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Michael Corradini
Wisconsin Institute of Nuclear Systems
Nuclear Engr. & Engr. Physics
University of Wisconsin - Madison
Institute of Nuclear Systems
MIT Rohsenow Symposium on Future Trends in Heat Transfer
ENERGY SUSTAINABILITY
Conditions Needed for Energy Sustainability:
‹ Economically
feasible technology
‹ Minimal by-product streams
‹ Acceptable land usage
‹ “Unlimited” supply of energy resource
‹ Neither the power source nor the technology to
exploit it can be controlled by a few nations/regions
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Nuclear energy systems meet these conditions and can
be part of the solution for future energy growth
(Electricity growth estimates range 1 - 4.5%/yr)
Institute of Nuclear Systems
MIT Rohsenow Symposium on Future Trends in Heat Transfer
Evolution of Nuclear Power Systems
Generation I
Early Prototype
Reactors
Generation II
Commercial Power Generation III
Reactors
Advanced
LWRs
Generation IV
•
•
•Shippingport
•Dresden,Fermi-I
•Magnox
•
•LWR: PWR/BWR
•CANDU
•VVER/RBMK
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Gen III
Gen II
1960
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Gen I
•System 80+ •AP1000
•ABWR
•ESBWR
1970
1980
Institute of Nuclear Systems
1990
2000
2010
•
Enhanced
Safety
More
economical
Minimized
Wastes
Proliferation
Resistance
Gen IV
2020
2030
MIT Rohsenow Symposium on Future Trends in Heat Transfer
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Advanced Light Water Reactors:
AP1000-Enhanced Passive Safety
Institute of Nuclear Systems
MIT Rohsenow Symposium on Future Trends in Heat Transfer
Advanced Light Water Reactors:
ESBWR-Simplified Operation & Safety
Natural Circulation
in the Vessel
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Passive Safety
Systems
Institute of Nuclear Systems
MIT Rohsenow Symposium on Future Trends in Heat Transfer
Advanced Light Water Reactors:
Multiphase Heat Transfer Issues
„
„
„
„
Passive systems can simplify construction and
operation but may complicate engr. analyses
Natural-circulation multiphase flow in complex
geometries (plant geom. dependent)
Condensation heat transfer with non-condensible
gases in reactor containment
Multiphase/multicomponent heat transfer in
safety analyses beyond the ALWR design base
In-vessel lower head cooling & Ex-vessel debris coolability
‹ Multiphase/multicomponent direct-contact heat-exchange
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‹
Institute of Nuclear Systems
MIT Rohsenow Symposium on Future Trends in Heat Transfer
A More Advanced LWR
The next logical step in path toward simplification ?
PWR
Steam g
ABWR
BWR/6
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A boiling water reactor
…without the boiling.
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SCWR
Institute of Nuclear Systems
ESBWR
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SUPERCRITICAL WATER REACTOR
Institute of Nuclear Systems
MIT Rohsenow Symposium on Future Trends in Heat Transfer
Heat Transfer in SCW Reactor:
Absence of boiling crisis (CHF),
but with heat transfer degradation
1400
40000
Jackson: 1.53
Jackson: 1.34
Jackson: 1.2335000
Bishop: 1.23
Bishop: 1.34
Bishop: 1.53 30000
Qlinear
1300
1200
Linear heat generation [W/m]
1100
Temperature [K]
25000
1000
20000
900
15000
800
10000
700
P/D
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600
0
0
0.5
1
1.5
2
2.5
3
Height of the core [m]
Institute of Nuclear Systems
MIT Rohsenow Symposium on Future Trends in Heat Transfer
900
110
800
100
700
90
600
80
500
70
400
60
300
50
200
Temperature (oC)
G (kg/m2s)
SCW Flow Control and Instabilities
40
Mass Velocity
Hot Side Temperature
100
30
0
20
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15
20
25
30
Power (kW)
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Institute of Nuclear Systems
MIT Rohsenow Symposium on Future Trends in Heat Transfer
Nuclear Fuel Recycle
Spent Fuel From
Commercial Plants
Direct
Disposal
Advanced,
Proliferation-Resistant
Recycling
AFCI
Advanced Separations
LWRs/ALWRs
Conventional
Reprocessing
PUREX
Pu
Spent
Fuel
Uranium
Gen IV Fuel Fabrication
Gen IV Fast Reactors
MOX
ADS Transmuter
LWRs/ALWRs
Repository
Repository
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Less U and Pu
Actinides
Fission Products
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Once Through
U and Pu
Fuel Cycle
Actinides
Fission Products
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Repository
Trace U and Pu
Trace Actinides
Less Fission Products
Advanced Proliferation Resistant
Fuel Cycle
MIT Rohsenow Symposium on Future Trends in Heat Transfer
Liquid-Metal-Cooled Fast Reactor (e.g. LFR)
Characteristics
• Pb or Pb/Bi coolant
• 550°C to 800°C outlet
temperature
• 120–400 MWe
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Key Benefit
• Waste minimization and
efficient use of uranium
resources
Institute of Nuclear Systems
MIT Rohsenow Symposium on Future Trends in Heat Transfer
Liquid Metal-Water Direct Contact HX
Steam
Advantages:
- Vigorous interaction between the
liquid metal and the water
- Excellent contact so smaller volume
is required to transfer the same
amount of energy.
Lsup
Lsat
L
- Potential replacement of IHX loop.
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=> Need to determine the local heat
transfer coefficient and flow stability
for a range of flow rates and regimes.
Institute of Nuclear Systems
MIT Rohsenow Symposium on Future Trends in Heat Transfer
DCHT via Xray Imaging
0 .3 0
E x p t . P = 0 .1 M p a
0 .2 5
αwater
0 .2 0
0 .1 5
0 .1 0
0 .0 5
0 .0 0
0 .0
0 .1
0 .2
0 .3
0 .4
0 .5
0 .6
D is ta n c e a b o v e in je c to r z [m ]
3000
2000
HTC
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t
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ar S
2.5
5
7.5
10
12.5
15
Distance from the Injector [cm]
Void [cm]
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(w/m2K)
1000
MIT Rohsenow Symposium on Future Trends in Heat Transfer
Very-High-Temperature Reactor (VHTR)
Characteristics
•
•
•
•
Helium coolant
1000°C outlet temp.
600 MWth
Water-cracking cycle
Key Benefit
Hydrogen production
by water-cracking
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•
Institute of Nuclear Systems
MIT Rohsenow Symposium on Future Trends in Heat Transfer
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GAS-COOLED
REACTOR
Institute of Nuclear Systems
MIT Rohsenow Symposium on Future Trends in Heat Transfer
Process Heat for Hydrogen Production
200 C
1000 C
Aqueous-phase
Carbohydrate
Reforming (ACR)
Hydrogen
Iodine/Sulfuric-Acid
Thermochemical
Process
Carbon
Recycle
H2, CO2
Hydrogen
Hydrogen
CATALYST
L
Nuclear
NuclearHeat
Heat
400 C
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I (Iodine)
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CxHy
LM Condensed Phase
Reforming (pyrolysis)
Institute of Nuclear Systems
I2
900 C
Rejected
Rejected
Heat
Heat100
100CC
2HI
I2
Liquid Metal
1O
2 2
H2
H2
AQUEOUS CARBOHYDRATE
O
Oxygen
xygen
2HI
+
H2SO4
I2 + H2O + SO2+H2O
H2O
H2SO4
1
2 O2
+
SO2+H2O
S(Sulfur)
Circulation
SO2
+
H2O
W
Water
ater
MIT Rohsenow Symposium on Future Trends in Heat Transfer
Micro-Nuclear Power Applications (NAE-Blanchard)
Direct Conversion
(Electricity from radiation used
to create ion-hole pair in PN Jnc)
Micro Thermoelectric or Thermionic Generator
P
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Self-Reciprocating Cantilever Wireless Transmitter
Institute of Nuclear Systems
MIT Rohsenow Symposium on Future Trends in Heat Transfer