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

Technical Report · Sun Jan 01 00:00:00 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
• Resource Relation: Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CANDU TYPE REACTORS
FUEL ELEMENTS
LOSS OF COOLANT
HEAT TRANSFER
HYDRAULICS
COMPUTER CALCULATIONS
PRESSURE GRADIENTS
REACTOR SAFETY
TEMPERATURE GRADIENTS
ACCIDENTS
ENERGY TRANSFER
FLUID MECHANICS
HEAVY WATER MODERATED REACTORS
MECHANICS
PRESSURE TUBE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
THERMAL REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210400 - Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated