Published October 1987 | Version v1
Report Restricted

Calculation of source terms for NUREG-1150

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

Availability note (English)

Available from NTIS, PC A03/MF A01 as DE88003633.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Pagination
15 p.
Report number
SAND--87-2051C

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
19058523
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ALGORITHMS; CONTAINMENT; FISSION PRODUCT RELEASE; FISSION PRODUCTS; R CODES; RADIOACTIVE EFFLUENTS; REACTOR ACCIDENTS; REACTOR SAFETY; RISK ASSESSMENT; S CODES; SOURCE TERMS; X CODES
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ISOTOPES; MATERIALS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; SAFETY; WASTES

Optional Information

Secondary number(s)
CONF-8710111--18.