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

Conference · Sat Dec 31 23:00:00 EST 1988

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]

---

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 (USA)
• Sponsoring Organization: DOE/NE
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6980411
• Report Number(s): EGG-M-89113; CONF-891103--72; ON: DE90010952
• Country of Publication: United States
• Language: English

Related Subjects

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