Impact of reductions in source term magnitudes on reactor accident consequences. [PWR; BWR]

Conference · Fri Jan 01 04:00:00 EST 1982

OSTI ID:5329531

Alpert, D J

Recently, NRC sponsored an evaluation of the technical basis for reactor accident source terms. The accident spectrum was divided into five groups, ranging from a full core-melt with uncontrolled release to a gap release with minimal leakage. For the purpose of decision making in such areas as siting and emergency response, NRC also defined a corresponding set of five generic LWR source terms, denoted SST1-5. A series of CRAC2 calculations has been made using these source terms. Consequence magnitudes for source terms SST1-5 were calculated and impact of source-term reductions on these magnitudes was examined.

• Research Organization: Sandia National Labs., Albuquerque, NM (USA)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 5329531
• Report Number(s): SAND-82-0268C; CONF-820609-2; ON: DE82006850
• Country of Publication: United States
• Language: English

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