PFB-CANDU Fuel Element LOCA Test experiment operating specification. Revision 1
Technical Report
·
OSTI ID:5491451
This document describes the experiment operating specifications for the PBF-CANDU Fuel Element LOCA Test to be conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory (INEL). The PBF-CANDU Fuel Element LOCA Test is sponsored jointly by Ontario Hydro and Atomic Energy of Canada Limited (AECL). Objectives are to provide an in-reactor evaluation of CANDU fuel element thermal-mechanical behavior during a postulated loss-of-coolant accident, and provide an experimental data base for evaluation of the transient fuel behavior code, ELOCA.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5491451
- Report Number(s):
- EGG-TFBP-6279-Rev.1; ON: DE84005029
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CANDU TYPE REACTORS
DATA ACQUISITION
FUEL ELEMENTS
HEAVY WATER MODERATED REACTORS
LOSS OF COOLANT
PBF REACTOR
PRESSURE TUBE REACTORS
PULSED REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SIMULATION
SPECIFICATIONS
TANK TYPE REACTORS
THERMAL REACTORS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CANDU TYPE REACTORS
DATA ACQUISITION
FUEL ELEMENTS
HEAVY WATER MODERATED REACTORS
LOSS OF COOLANT
PBF REACTOR
PRESSURE TUBE REACTORS
PULSED REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SIMULATION
SPECIFICATIONS
TANK TYPE REACTORS
THERMAL REACTORS