Assessment of prism responses to loss of flow events
Conference
·
OSTI ID:10173120
- Brookhaven National Lab., Upton, NY (United States)
- 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
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