Reliability analysis of MURR safety functions
This study investigated use of improved methods of reliability analysis (over those used in the WASH-1400 report) in reactor safety studies. The methods of event and fault trees that are used to analyze the accident sequences and the safety functions are described. Most importantly, an improvement over the current methods is used to construct the correct mathematical relationship between a system and its components a more advanced method of estimating failure rates and failure probabilities is presented, and a methodology is introduced solving existing problems in past studies (that had employed subjective probabilities). These methods are investigated in the framework of the University of Missouri Research Reactor (MURR) safety functions. Two significant classes of accidents (Loss of Flow and Loss of Coolant) are analyzed in this research project. Examples are presented showing the difference in the results from using the WASH.
- Research Organization:
- Missouri Univ., Columbia (USA)
- OSTI ID:
- 6826408
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
DATA
ENRICHED URANIUM REACTORS
EXPERIMENTAL DATA
INFORMATION
LOSS OF COOLANT
LOSS OF FLOW
MATHEMATICAL LOGIC
MURR REACTOR
NUMERICAL DATA
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SYSTEMS ANALYSIS
TANK TYPE REACTORS
TRAINING REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS