Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects

NEA-1783 IFPE/CANDU-FIO-131.

last modified: 16-JAN-2023 | catalog | new | search |

NEA-1783 IFPE/CANDU-FIO-131.

IFPE/CANDU-FIO-131, CANDU experiment FIO-131 Fuel Behaviour under LOCA Conditions

NAME, COMPUTER, PROBLEM, STATUS, REFERENCES, LANGUAGE, AUTHOR, MATERIAL, CATEGORIES

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1. NAME OF EXPERIMENT

IFPE/CANDU-FIO-131

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2. COMPUTERS

To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.

Program name	Package id	Status	Status date
IFPE/CANDU-FIO-131	NEA-1783/02	Arrived	16-JAN-2023

Machines used:

Package ID	Orig. computer	Test computer
NEA-1783/02	Many Computers

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3. DESCRIPTION

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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9. STATUS

Package ID	Status date	Status
NEA-1783/02	16-JAN-2023	Masterfiled restricted

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10. REFERENCES

NEA-1783/02, 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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12. PROGRAMMING LANGUAGE(S) USED

No specified programming language

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15. NAME AND ESTABLISHMENT OF AUTHORS

Atomic Energy of Canada, Ltd.

Chalk River Laboratories

Chalk River

Ontario, K0J 1J0

CANADA

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16. MATERIAL AVAILABLE

NEA-1783/02

FIO-131_Experiment.pdf   EXP-FIO-131 Experiment information
FIO-131_Report.txt       EXP-FIO-131 Experiment information
Figures (TIF and GIF)
Table 1.txt              F10-131 Experiment A10H Fuel Element Data
Table 2.txt              Average Element Powers for Exp-FIO-131 Fuel Element
During Soak Irradiation Period
Table 3.txt              Typical Values of Parameters During Steady-State
Irradiation Periods
Table 4.txt              In-reactor Test Parameters from LOCA Transient
Table 5.txt              Exp-FIO-131 Recorded Temperature and Pressure Data
from Second Transient
Table 6.txt              Maximum Values of Parameters Measured During the
Blowdown Transients
Table 7.txt              Power History for Second Transient
Table 8.txt              A10H Fuel Element Post-Test Diameters (mm)
Table 9.txt              Post-Irradiation UO2 Grain Size Measurements of
Element A10H from Exp-FIO-131

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17. CATEGORIES

Y. Integral Experiments Data, Databases, Benchmarks

Keywords: CANDU, fuel behaviour, loss-of-coolant accident.