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Loft uncertainty analysis methodology

Journal Article · · Am. Soc. Mech. Eng., (Pap.); (United States)
OSTI ID:5113675
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., P.O. Box 1625, Idaho Falls, Idaho
DOE Contract Number:
AC07-76ID01570
OSTI ID:
5113675
Journal Information:
Am. Soc. Mech. Eng., (Pap.); (United States), Journal Name: Am. Soc. Mech. Eng., (Pap.); (United States) Vol. 83-HT-107; ISSN ASMSA
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
CALCULATION METHODS
DATA ANALYSIS
DATA COVARIANCES
LOFT REACTOR
MEASURING METHODS
PWR TYPE REACTORS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS