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Core melt progression and consequence analysis methodology development in support of the Savannah River Reactor PSA

Conference ·
OSTI ID:10163594
 [1];  [1];  [2];  [2];  [2]
  1. Westinghouse Savannah River Co., Aiken, SC (United States)
  2. Science Applications International Corp., Albuquerque, NM (United States)
+ Show Author Affiliations
A three-level Probabilistic Safety Assessment (PSA) of production reactor operation has been underway since 1985 at the US Department of Energy`s Savannah River Site (SRS). The goals of this analysis are to: Analyze existing margins of safety provided by the heavy-water reactor (HWR) design challenged by postulated severe accidents; Compare measures of risk to the general public and onsite workers to guideline values, as well as to those posed by commercial reactor operation; and Develop the methodology and database necessary to prioritize improvements to engineering safety systems and components, operator training, and engineering projects that contribute significantly to improving plant safety. PSA technical staff from the Westinghouse Savannah River Company (WSRC) and Science Applications International Corporation (SAIC) have performed the assessment despite two obstacles: A variable baseline plant configuration and power level; and a lack of technically applicable code methodology to model the SRS reactor conditions. This paper discusses the detailed effort necessary to modify the requisite codes before accident analysis insights for the risk assessment were obtained.
Research Organization:
Westinghouse Savannah River Co., Aiken, SC (United States)
Sponsoring Organization:
USDOE, Washington, DC (United States)
DOE Contract Number:
AC09-89SR18035
OSTI ID:
10163594
Report Number(s):
WSRC-MS--92-227; CONF-930116--1; ON: DE92016889
Country of Publication:
United States
Language:
English

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Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220600
220900
97 MATHEMATICS AND COMPUTING
990200
C CODES
COMPUTER CODES
CORIUM
FISSION PRODUCT RELEASE
FUEL-COOLANT INTERACTIONS
HEAT TRANSFER
HYDRAULICS
M CODES
MATHEMATICS AND COMPUTERS
MELTDOWN
MODIFICATIONS
PRODUCTION REACTORS
REACTOR SAFETY
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
RISK ASSESSMENT
SAVANNAH RIVER PLANT