Development of a PIRT (phenomena identification and ranking table) for a postulated double-ended guillotine break in a production reactor

Conference · Sun Jan 01 00:00:00 EST 1989

DOI:https://doi.org/10.1016/0029-5493(92)90032-Q· OSTI ID:6980411

Hanson, R G; Wilson, G E; Ortiz, M G ^[1]; Griggs, D P ^[2]

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1. EG and G Idaho, Inc., Idaho Falls, ID (USA)
2. Savannah River Lab., Aiken, SC (USA)

The US Nuclear Regulatory Commission has developed a generic methodology to quantify the uncertainty in best estimate computer codes used to license commercial light water reactors. This same methodology is equally applicable to other reactor designs with regards to providing a technical basis which supports the establishment and demonstration of compliance with safe operating margins. One of the cornerstones of the method is the identification and ranking of phenomena that are important to the postulated scenario. This paper references descriptions of the total methodology, describes the first three steps (i.e, through the identification and ranking of phenomena), and summarizes the results of the application of the methodology to a double-ended guillotine break loss of coolant accident in a production reactor. 6 refs., 8 figs., 5 tabs.

• Research Organization: EG and G Idaho, Inc., Idaho Falls, ID (United States)
• Sponsoring Organization: DOE/NE
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6980411
• Report Number(s): EGG-M-89113; CONF-891103-72; ON: DE90010952
• Resource Relation: Journal Volume: 136; Journal Issue: 3; Conference: Winter meeting of the American Nuclear Society, San Francisco, CA (USA), 26-30 Nov 1989
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
LOSS OF COOLANT
C CODES
PRODUCTION REACTORS
PWR TYPE REACTORS
DATA COVARIANCES
ECCS
FAILURE MODE ANALYSIS
FLOWSHEETS
HEAT TRANSFER
HYDRAULICS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
ACCIDENTS
COMPUTER CODES
COOLING SYSTEMS
DIAGRAMS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID MECHANICS
MECHANICS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR PROTECTION SYSTEMS
REACTORS
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
220700 - Nuclear Reactor Technology- Plutonium & Isotope Production Reactors
990200 - Mathematics & Computers