PBF-CANDU fuel element LOCA test experiment predictions. Revision 1

Technical Report · Sun Jan 01 04:00:00 EST 1984

OSTI ID:5222785

Smith, R H; Martinson, Z R

A loss-of-coolant test sponsored jointly by Ontario Hydro and Atomic Energy of Canada Limited (AECL) will be performed in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory (INEL). The test will provide both an in-reactor evaluation of CANDU fuel element thermal mechanical behavior during a postulated Loss-of-Coolant Accident and an experimental data base for evaluation of the Canadian transient fuel behavior code, ELOCA. The PFB-CANDU test train is comprised of four independently shrouded CANDU design fuel elements installed in symmetric orientations in a modified PBF test assembly. Three of the fuel elements were preirradiated in the NRX reactor to approximately 5000 MWd/t (120 MWh/kgU) at approx. 53 kW/m, and the fourth fuel element is unirradiated.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5222785
• Report Number(s): EGG-TFBP-6399-Rev.1; ON: DE84008020
• Country of Publication: United States
• Language: English

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