LOFT LOCA: WHAM6 model and code application
This report documents the WHAM6 analysis of a loss-of-coolant accident (LOCA) pipe break at the reactor vessel. Data derived from this document is to be used to generate loads for the LOCA analysis of the reactor internals.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6606934
- Report Number(s):
- LTR-114-100
- 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
COMPUTER CALCULATIONS
COMPUTER CODES
LOFT REACTOR
LOSS OF COOLANT
MATHEMATICAL MODELS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
RESEARCH AND TEST REACTORS
TANK TYPE REACTORS
TEST REACTORS
W CODES
WATER COOLED REACTORS
WATER HAMMER
WATER MODERATED REACTORS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CALCULATIONS
COMPUTER CODES
LOFT REACTOR
LOSS OF COOLANT
MATHEMATICAL MODELS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
RESEARCH AND TEST REACTORS
TANK TYPE REACTORS
TEST REACTORS
W CODES
WATER COOLED REACTORS
WATER HAMMER
WATER MODERATED REACTORS