Published April 1998 | Version v1
Report Restricted

Preliminary phenomena identification and ranking tables for simplified boiling water reactor Loss-of-Coolant Accident scenarios

Creators

Description

For three potential Loss-of-Coolant Accident (LOCA) scenarios in the General Electric Simplified Boiling Water Reactors (SBWR) a set of Phenomena Identification and Ranking Tables (PIRT) is presented. The selected LOCA scenarios are typical for the class of small and large breaks generally considered in Safety Analysis Reports. The method used to develop the PIRTs is described. Following is a discussion of the transient scenarios, the PIRTs are presented and discussed in detailed and in summarized form. A procedure for future validation of the PIRTs, to enhance their value, is outlined. 26 refs., 25 figs., 44 tabs

Availability note (English)

Available from INIS in electronic form; ALSO AVAILABLE FROM OSTI AS TI98004872; NTIS; GPO

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Additional details

Publishing Information

Imprint Pagination
156 p.
Report number
NUREG/CR--6472

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
29041592
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BWR TYPE REACTORS; HAZARDS; LOSS OF COOLANT; SAFETY ANALYSIS
Descriptors DEC
ACCIDENTS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Contract/Grant/Project number
Contract AC02-76CH00016
Funding organization
Nuclear Regulatory Commission, Washington, DC (United States)
Secondary number(s)
BNL-NUREG--52501