PBF-CANDU fuel element LOCA test: experiment specification document
Technical Report
·
OSTI ID:5338693
The objectives of the PBF-CANDU Fuel Element LOCA tests are to: (1) provide an in-reactor evaluation of CANDU fuel element thermal-mechanical behavior during a postulated loss-of-coolant accident, and (2) provide an experimental data base for evaluation of the transient fuel behavior code, ELOCA. The purpose of this document is to provide a preliminary identification of the fuel, test train, instrumentation, and PBF operational requirements for performance of the PBF-CANDU LOCA test.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5338693
- Report Number(s):
- EGG-TFBP-5645; ON: DE82015615
- Country of Publication:
- United States
- Language:
- English
Similar Records
PBF-CANDU fuel element LOCA test experiment predictions
PBF-CANDU fuel element LOCA test experiment predictions. Revision 1
PFB-CANDU Fuel Element LOCA Test experiment operating specification. Revision 1
Technical Report
·
Sat Oct 01 00:00:00 EDT 1983
·
OSTI ID:5338693
PBF-CANDU fuel element LOCA test experiment predictions. Revision 1
Technical Report
·
Sun Jan 01 00:00:00 EST 1984
·
OSTI ID:5338693
PFB-CANDU Fuel Element LOCA Test experiment operating specification. Revision 1
Technical Report
·
Tue Nov 01 00:00:00 EST 1983
·
OSTI ID:5338693
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CANDU TYPE REACTORS
FUEL ELEMENTS
LOSS OF COOLANT
PERFORMANCE TESTING
PRESSURE GRADIENTS
THERMAL STRESSES
REACTOR SAFETY
ACCIDENTS
HEAVY WATER MODERATED REACTORS
PRESSURE TUBE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
STRESSES
TESTING
THERMAL REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210400 - Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CANDU TYPE REACTORS
FUEL ELEMENTS
LOSS OF COOLANT
PERFORMANCE TESTING
PRESSURE GRADIENTS
THERMAL STRESSES
REACTOR SAFETY
ACCIDENTS
HEAVY WATER MODERATED REACTORS
PRESSURE TUBE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
STRESSES
TESTING
THERMAL REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210400 - Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated