Assessment of prism responses to loss of flow events

Conference · Tue Sep 01 00:00:00 EDT 1992

OSTI ID:10173120

Slovik, G C; Van Tuyle, G J ^[1]; Sands, S ^[2]

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1. Brookhaven National Lab., Upton, NY (United States)
2. Nuclear Regulatory Commission, Washington, DC (United States)

The Nuclear Regulatory Commission (NRC), with Brookhaven national Laboratory providing technical support, is continuing a preapplication review of the 471 MWt, advanced liquid metal reactor (ALMR), PRISM by General Electric. The revised design has been evaluated using the SSC code, for a series of loss of flow events (LOF) with and without gas expansion modules (GEMs). These devices have a net worth of 69{cents} and have reduced the seriousness of the LOF in PRISM. However, it was found that the extremely low probability case of an instantaneous loss of 4 EM pumps without scram could lead to sodium boiling even with the GEMs.

• Research Organization: Brookhaven National Lab., Upton, NY (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 10173120
• Report Number(s): BNL-NUREG-47818; CONF-921003-1; ON: DE92019218; TRN: 92:030134
• Resource Relation: Conference: ANP`92: international conference on design and safety of advanced nuclear power plants,Tokyo (Japan),25-29 Oct 1992; Other Information: PBD: [1992]
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
LOSS OF FLOW
DESIGN
EVALUATION
REACTOR SAFETY
REACTOR SHUTDOWN
AFTER-HEAT REMOVAL
S CODES
FUEL ELEMENTS
REACTOR VESSELS
THERMAL EXPANSION
PUMPS
SCRAM
220900
210500
POWER REACTORS
BREEDING