INP
Irradiation Test of Linear Variable
Differential Transformers in the
WWR-K core
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2
A. SHAIMERDENOV,
A.BEISEBAEV,
Sh. GIZATULIN,
P. CHAKROV
M. TANIMOTO,
N. KIMURA,
K. TSUCHIYA,
H. KAWAMURA
1) The Kazakhstan Institute of Nuclear Physics (KINP), Ibragimov, 1, 050032, Almaty, Republic of Kazakhstan
2) The Japan Atomic Energy Agency (JAEA), Oarai-machi, Higashi-ibaraki-gun, Ibaraki-ken 311-1393, Japan
IAEA Technical meeting on In-pile testing and instrumentation for development of generation-IV fuels and
structural materials, 21-24 August 2012, Halden, Norway
WWR-K RESEARCH REACTOR
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Commissioned in 1967
Continuous operated till 1988
1988-1998: upgrade, licensing
Re-started in 1998
Power Rating: 6 MW
Max thermal neutron flux: 11014 cm-2s-1
Fuel enrichment: 36% in 235U
Moderator /coolant: light water
Reflector: beryllium/ water
Utilization:
- Isotope production;
- Materials radiation tests;
- Neutron activation analysis;
- Neutron physics research;
- Transmutation doping of Silicon.
IAEA Technical meeting on In-pile testing and instrumentation for development of generation-IV fuels and
structural materials, 21-24 August 2012, Halden, Norway
2
TRANSFORMER-TYPED FISSION PRODUCT
PRESSURE GAUGE
Bellows
Spring
Linear voltage
differential transformer (LVDT)
φ14
Pressure tube
~150
unit : mm
DIFFERENTIAL TRANSFORMERS
Type
Items
Conventional Linear Voltage
Differential Transformer
Improved Linear Voltage
Differential Transformer
Coil materials
Ceramic covered wire
MI cable
PbO·SiO2·TiO2·MgO
MgO, Al2O3
Photograph
Insulator
IAEA Technical meeting on In-pile testing and instrumentation for development of generation-IV fuels and
structural materials, 21-24 August 2012, Halden, Norway
3
CROSS SECTION OF THE INNER CAPSULE
A gap 1 mm thick is available between
the channel wall and the inner capsule;
the gap filled with helium gas. Variation
of helium pressure in the gap within a
range from 30 to 105 Pa has made it
possible controlling of the transformer
temperature within a range from 300°C
to 200°C.
Inner capsule of the irradiation device
Irradiation device in assemblage
IAEA Technical meeting on In-pile testing and instrumentation for development of generation-IV fuels and
structural materials, 21-24 August 2012, Halden, Norway
4
THE REACTOR CORE MAP TO BE USED IN STUDIES
OF DIFFERENTIAL TRANSFORMERS
Neutron flux density in cell 5-9:
thermal: (5.90.9)∙1013 cm-2s-1
fast:
(7.92.0)∙1012 cm-2s-1
Irradiation test of LVDT, started on April 6, 2011
IAEA Technical meeting on In-pile testing and instrumentation for development of generation-IV fuels and
structural materials, 21-24 August 2012, Halden, Norway
5
UNIVERSAL LOOP FACILITY
2
6
5
1
4
3
Schematic circuit of ULF system components and devices in the reactor building
1 – reactor core;
2 – ULF monitoring systems;
3 – gas-vacuum communication systems;
4 – the power-supply and gas-supply systems;
5 –ULF control room;
6 – microcontrollers (ADAM)
IAEA Technical meeting on In-pile testing and instrumentation for development of generation-IV fuels and
structural materials, 21-24 August 2012, Halden, Norway
6
BOX DIAGRAM
OF THE ULF GAS-VACUUM COMMUNICATIONS
1 – irradiation channel;
2 – manual valve to isolate the irradiation tube
after degassing, when transporting and after
completion of trials;
3 – pressure sensors, which provide electronic
control of pressure;
4 – electrically-driven valves;
5 – a unit for working gas choice/supply;
6 – vacuum pump;
7 –irradiated gas collectors.
IAEA Technical meeting on In-pile testing and instrumentation for development of generation-IV fuels and
structural materials, 21-24 August 2012, Halden, Norway
7
MEASURING MEANS
No.
(1)
Name
Thermocouple
(K-type T/C)
(2) Electric heater
Function
Specification
Measurement and control of length : 6 m
irradiation
temperature
inside
diameter : 1.6 mm
irradiation capsule
Heating and control of the DTPG
length : 6 m
irradiation temperature
diameter : 1.5 or 2 mm
Self-Powered Neutron
(3) Detector
Measurement of the neutron flux
(Rh-type SPND)
Fast neutron
(4)
Evaluation of fast neutron fluence
fluence monitor
Qnty
(4)
(2)
length : 6 m
Detector : 2×70mm
(2)
diameter : 1.6 mm
54Fe(n,p)54Mn
(3)
IAEA Technical meeting on In-pile testing and instrumentation for development of generation-IV fuels and
structural materials, 21-24 August 2012, Halden, Norway
8
DESIGN OF IRRADIATION CAPSULE
Irradiation Test Measuring System
Conceptual design
of Irradiation Capsule
SPND
Temp.
Voltage
Measuring Items
Improved LVDT
Conventional LVDT
T/C
- Voltage across the LVDT 2nd coil
- LVDT Temperature
- LVDT Neutron flux
- LVDT Insulation
- LVDT Resistance
- LVDT Impedance
SPND
Heater
Install
WWR-K core
IAEA Technical meeting on In-pile testing and instrumentation for development of generation-IV fuels and
structural materials, 21-24 August 2012, Halden, Norway
9
ELECTRICAL CIRCUITS IN IRRADIATION TEST OF LVDT
Temperature Controller
adapter
Heater
T/C-1
adapter
T/C
T/C-2
0~1000oC
(Type-K)
Constant-current AC Power Supplier
LVDT-1(E1)
adapter
LVDT
LVDT-1(E2)
LVDT-2(E1)
Data Collection System
LVDT-2(E2)
Microcontrollers
ADAM 5000E
WWR-K
IAEA Technical meeting on In-pile testing and instrumentation for development of generation-IV fuels and
structural materials, 21-24 August 2012, Halden, Norway
10
EXPECTED RESULTS IN THIS IRRADIATION TEST
Measuring Procedure
Expected Results
Evaluation of LVDT output
1st coil
Voltmeter
R
For example
e1  e2
e1  e2
Stabilization
Voltmeter
Insulation Resistance
e1
V
Metal rod
Constant-current
AC power supplier
e2
Schematic diagram of LVDT
2nd coil
R
Results of differential transformer under un-irradiation ( example)
Conventional LVDT
(Ceramic covered wire)
Improved LVDT
(MI cable)
Input condition
for 1st coil
50mA, 1kHz
100mA, 1kHz
Voltage across
2nd coil (e1, e2)
0.9 – 1.1 V
60 – 70 mV
Reactor
operation
Reactor
operation
Reactor
operation
Reactor
operation
Neutron Fluence
- Experiments on LVDT temperature variation
- Experiments on variation of input condition
for 1st coil
IAEA Technical meeting on In-pile testing and instrumentation for development of generation-IV fuels and
structural materials, 21-24 August 2012, Halden, Norway
11
RESULTS OF IRRADIATION LVDT TEST (1)
Temporal variation in the SPND readings
Temporal variation in the transformer temperature
Temporal variation in the voltage across coils of
the ceramic-wire transformer
Temporal variation in the voltage across coils of
the MI-cable transformer
IAEA Technical meeting on In-pile testing and instrumentation for development of generation-IV fuels and
structural materials, 21-24 August 2012, Halden, Norway
12
RESULTS OF IRRADIATION LVDT TEST (2)
Temporal variation in the resistance of the
MI-cable transformer
Temporal variation in the resistance
of the ceramic-wire transformer
Temporal variation in the insulation
resistance of the MI-cable transformer coils
Temporal variation in the insulation resistance
of the ceramic-wire transformer coils
IAEA Technical meeting on In-pile testing and instrumentation for development of generation-IV fuels and
structural materials, 21-24 August 2012, Halden, Norway
13
TRANSFORMATION RATIO
RATIO
Primary coil in conventional differential
transformer breaks, whereas the improved
differential transformer continues to work
171 days
Time, d
The MI-cable LVDT transformation ratio was unvaried for the entire period of tests, staying
independent of temperature within a range from room temperature to 300 °C.
The ceramic wire LVDT transformation ratio reduced permanently in course of irradiation for
171 days (from 0.22 to 0.12), changing dramatically at a temperature higher than 270 °C.
IAEA Technical meeting on In-pile testing and instrumentation for development of generation-IV fuels and
structural materials, 21-24 August 2012, Halden, Norway
14
CONCLUSION
The conventional linear variable differential transformer operated for 171 days at 6
MW. Then primary coil was broken.
The improved linear variable differential transformer operated for entire test period
(228 days at 6 MW), staying serviceable.
The improved linear variable differential transformer demonstrated stable
operation under long-term in-reactor irradiation for entire test period.
IAEA Technical meeting on In-pile testing and instrumentation for development of generation-IV fuels and
structural materials, 21-24 August 2012, Halden, Norway
15
Thank you for your attention!
IAEA Technical meeting on In-pile testing and instrumentation for development of generation-IV fuels and
structural materials, 21-24 August 2012, Halden, Norway
16