A common sense approach to consequence analysis at a large DOE site
Conference
·
OSTI ID:6669151
The primary objective of the Probabilistic Safety Assessment (PSA) at the U. S. Department of Energy (DOE) Savannah River Site (SRS) is to quantify health and economic risks posed by K Reactor operation to the nearby offsite and onsite areas from highly unlikely severe accidents. The overall risk analyses have also been instrumental as defensible bases for analyzing existing safety margins of the restart configuration; determining component, human action, and engineering system vulnerabilities; comparing measures of risk to DOE and commercial guidelines; and prioritizing risk-significant improvements. The key final phase of these probabilistic risk calculations, a third level of analysis or Level 3 PSA, requires the determination of the conditional consequences to onsite workers and the DOE reservation facilities, given low-probability, postulated fuel-melting accidents with accompanying atmospheric releases have occurred. A modified version of the commercial reactor-based MACCS 1.5 code, MACCS/ON, is used in the context of the SRS PSA to perform the consequence determinations. The updated code is applicable to other large DOE sites for risk analyses of facility operations, and is compatible with proposed modifications planned by code developers, Sandia National Laboratories.
- Research Organization:
- Westinghouse Savannah River Co., Aiken, SC (United States)
- Sponsoring Organization:
- DOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 6669151
- Report Number(s):
- WSRC-MS-92-254-Rev.1; CONF-9208117--23-Rev.1; ON: DE93006327
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
54 ENVIRONMENTAL SCIENCES
540130 -- Environment
Atmospheric-- Radioactive Materials Monitoring & Transport-- (1990-)
ACCIDENTS
ATMOSPHERIC PRECIPITATIONS
DOSES
ENVIRONMENTAL TRANSPORT
EVACUATION
GAUSSIAN PROCESSES
HAZARDS
HEALTH HAZARDS
MASS TRANSFER
METEOROLOGY
NATIONAL ORGANIZATIONS
PLUMES
RADIATION DOSES
RADIONUCLIDE MIGRATION
RISK ASSESSMENT
SAFETY
SAVANNAH RIVER PLANT
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220900* -- Nuclear Reactor Technology-- Reactor Safety
54 ENVIRONMENTAL SCIENCES
540130 -- Environment
Atmospheric-- Radioactive Materials Monitoring & Transport-- (1990-)
ACCIDENTS
ATMOSPHERIC PRECIPITATIONS
DOSES
ENVIRONMENTAL TRANSPORT
EVACUATION
GAUSSIAN PROCESSES
HAZARDS
HEALTH HAZARDS
MASS TRANSFER
METEOROLOGY
NATIONAL ORGANIZATIONS
PLUMES
RADIATION DOSES
RADIONUCLIDE MIGRATION
RISK ASSESSMENT
SAFETY
SAVANNAH RIVER PLANT
US AEC
US DOE
US ERDA
US ORGANIZATIONS