LOFT uncertainty-analysis methodology
Conference
·
OSTI ID:5657665
The methodology used for uncertainty analyses of measurements in the Loss-of-Fluid Test (LOFT) nuclear reactor safety research program is described and compared with other methodologies established for performing uncertainty analyses.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5657665
- Report Number(s):
- EGG-M-08883; CONF-830702-27; ON: DE84000563
- 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
DATA COVARIANCES
LOFT REACTOR
PWR TYPE REACTORS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
SAFETY
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
DATA COVARIANCES
LOFT REACTOR
PWR TYPE REACTORS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
SAFETY
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS