Analysis of postulated unscrammed loss of flow in SAFR using SSC
- Brookhaven National Lab., Upton, NY (USA)
Brookhaven National Laboratory is providing technical assistance to the US Nuclear Regulatory Commission in reviewing two advanced liquid-metal reactor (LMR) designs in order to address the licensability of these innovative concepts. The designs, PRISM and SAFR are being proposed by General Electric Company and Rockwell International (RI), respectively. Brookhaven National Laboratory has utilized the super system code (SSC) to independently evaluate the LMR reactor system response during several postulated unscrammed events. This paper describes the SAFR reactor responses to a beyond-design base event where forced cooling is lost. A similar transient analysis has already been reported for PRISM.
- OSTI ID:
- 5529512
- Report Number(s):
- CONF-881011--
- Journal Information:
- Transactions of the American Nuclear Society; (USA), Journal Name: Transactions of the American Nuclear Society; (USA) Vol. 57; ISSN TANSA; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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ACCIDENTS
ALKALI METALS
BNL
BOILERS
COMPUTER CODES
COOLING SYSTEMS
DESIGN BASIS ACCIDENTS
ELEMENTS
ENERGY SYSTEMS
ENERGY TRANSFER
FEEDWATER
HEAT TRANSFER
HYDROGEN COMPOUNDS
LICENSING
LIQUID METAL COOLED REACTORS
LOSS OF FLOW
METALS
NATIONAL ORGANIZATIONS
OXYGEN COMPOUNDS
PRIMARY COOLANT CIRCUITS
REACTIVITY
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR LICENSING
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
S CODES
SAFETY
SCRAM
SHUTDOWN
SODIUM
STEAM GENERATORS
TRANSIENTS
US AEC
US DOE
US ERDA
US NRC
US ORGANIZATIONS
VAPOR GENERATORS
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