Calculation of source terms for NUREG-1150
- 1. Sandia National Labs., Albuquerque, NM (USA)
Description
The source terms estimated for NUREG-1150 are generally based on the Source Term Code Package (STCP), but the actual source term calculations used in computing risk are performed by much smaller codes which are specific to each plant. This was done because the method of estimating the uncertainty in risk for NUREG-1150 requires hundreds of source term calculations for each accident sequence. This is clearly impossible with a large, detailed code like the STCP. The small plant-specific codes are based on simple algorithms and utilize adjustable parameters. The values of the parameters appearing in these codes are derived from the available STCP results. To determine the uncertainty in the estimation of the source terms, these parameters were varied as specified by an expert review group. This method was used to account for the uncertainties in the STCP results and the uncertainties in phenomena not considered by the STCP
Additional details
Publishing Information
- Imprint Title
- Proceeding of the US Nuclear Regulatory Commission fifteenth water reactor safety information meeting: Volume 1, Planary sessions, reactor licensing topics, NUREG-1150, risk analysis/PRA applications, innovative concepts for increased safety of advanced power reactors, severe accident modeling and analysis
- Journal Page Range
- p. 115-129.
- Report number
- NUREG/CP--0091-Vol.1
Conference
- Title
- 15. water reactor safety information meeting.
- Dates
- 26-30 Oct 1987.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19088506
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALGORITHMS; COMPUTER CODES; GRAND GULF-1 REACTOR; GRAND GULF-2 REACTOR; NUCLEAR POWER PLANTS; PEACH BOTTOM-2 REACTOR; PEACH BOTTOM-3 REACTOR; R CODES; RISK ASSESSMENT; S CODES; SEQUOYAH-1 REACTOR; SEQUOYAH-2 REACTOR; SOURCE TERMS; SURRY-1 REACTOR; SURRY-2 REACTOR; SURRY-3 REACTOR; SURRY-4 REACTOR; X CODES
- Descriptors DEC
- BWR TYPE REACTORS; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS