NEA-1783 IFPE/CANDU-FIO-131.
IFPE/CANDU-FIO-131, CANDU experiment FIO-131 Fuel Behaviour under LOCA Conditions
NAME OF EXPERIMENT, COMPUTER, DESCRIPTION OF EXPERIMENT, STATUS, REFERENCES, LANGUAGE, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| IFPE/CANDU-FIO-131 | NEA-1783/01 | Arrived | 12-APR-2007 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-1783/01 | Many Computers |
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3. DESCRIPTION OF EXPERIMENT
The EXP-FIO-131 experiment, performed at the Chalk River Laboratories in 1983, was a part of an experimental program on fuel performance under high-temperature transient conditions such as those associated with the onset of a loss of coolant accident (LOCA).
The main purpose of the EXP-FIO-131 experiment was to provide quantitative code verification data.
An instrumented, unirradiated, Zircaloy-sheathed UO2 fuel element assembly was subjected to a coolant depressurization (blowdown) transient in the X-2 pressurized water loop of the NRX reactor. The fuel element used 1.3 wt% U235 in uranium dioxide fuel clad with Zircaloy-4 sheath material.
The fuel assembly was instrumented with one functional centreline fuel thermocouple, a peripheral fuel thermocouple, six sheath thermocouples, four coolant thermocouples, an internal gas pressure transducer, and a pressure transducer to monitor coolant pressures at the fuel assembly outlet.
Post-irradiation examination (PIE) of the fuel element assembly included visual examination, sheath profilometry measurements, neutron radiography, and metallography, including fuel grain size measurements. Chemical burnup and fission-gas measurements were not done.
The EXP-FIO-131 experiment, performed at the Chalk River Laboratories in 1983, was a part of an experimental program on fuel performance under high-temperature transient conditions such as those associated with the onset of a loss of coolant accident (LOCA).
The main purpose of the EXP-FIO-131 experiment was to provide quantitative code verification data.
An instrumented, unirradiated, Zircaloy-sheathed UO2 fuel element assembly was subjected to a coolant depressurization (blowdown) transient in the X-2 pressurized water loop of the NRX reactor. The fuel element used 1.3 wt% U235 in uranium dioxide fuel clad with Zircaloy-4 sheath material.
The fuel assembly was instrumented with one functional centreline fuel thermocouple, a peripheral fuel thermocouple, six sheath thermocouples, four coolant thermocouples, an internal gas pressure transducer, and a pressure transducer to monitor coolant pressures at the fuel assembly outlet.
Post-irradiation examination (PIE) of the fuel element assembly included visual examination, sheath profilometry measurements, neutron radiography, and metallography, including fuel grain size measurements. Chemical burnup and fission-gas measurements were not done.
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NEA-1783/01, included references:
- P.J. Fehrenbach, J.A. Walsworth, R. C. Spencer, W.R. Chase and R. D. Delaney:'In-Reactor LOCA Tests of Zircaloy-Sheathed UO2 Fuel at Chalk River', AECL
Report AECL-8974, June 1985 (in Proceedings of 6th CNS Annual Conference, June
1985, p.11.14-11.19)
- J.A. Walsworth, P.J. Fehrenbach, and R. C. Spencer:
'Comparison between ELOCA Code Calculations and CANDU Fuel Behaviour Under LOCA
Conditions', Proceedings of 6th CNS Annual Conference, June 1985, p.11.28-11.35
- EXP-FIO-131 Experiment (AECL, Chalk River Labs) document
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NEA-1783/01
Figures (TIF and GIF formats)Ancillary data (reports in PDF form)
Table 1 F10-131 Experiment A10H Fuel Element Data
Table 2 Average Element Powers for Exp-FIO-131 Fuel Element During Soak
Irradiation Period
Table 3 Typical Values of Parameters During Steady-State Irradiation Periods
Table 4 In-reactor Test Parameters from LOCA Transient
Table 5 Exp-FIO-131 Recorded Temperature and Pressure Data from Second
Transient
Table 6 Maximum Values of Parameters Measured During the Blowdown Transients
Table 7 Power History for Second Transient
Table 8 A10H Fuel Element Post-Test Diameters (mm)
Table 9 Post-Irradiation UO2 Grain Size Measurements of Element A10H from
Exp-FIO-131
FIO-131 experiment description in electronic form
Keywords: CANDU, fuel behaviour, loss-of-coolant accident.