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Title: Results of the Level 1 probabilistic risk assessment (PRA) of internal events for heavy water production reactors

Abstract

A full-scope probabilistic risk assessment (PRA) is being performed for the Savannah River site (SRS) production reactors. The Level 1 PRA for the K Reactor has been completed and includes the assessment of reactor systems response to accidents and estimates of the severe core melt frequency (SCMF). The internal events spectrum includes those events related directly to plant systems and safety functions for which transients or failures may initiate an accident. The SRS PRA has three principal objectives: improved understanding of SRS reactor safety issues through discovery and understanding of the mechanisms involved. Improved risk management capability through tools for assessing the safety impact of both current standard operations and proposed revisions. A quantitative measure of the risks posed by SRS reactor operation to employees and the general public, to allow comparison with declared goals and other societal risks.

Authors:
; ; ; ; ;
Publication Date:
Research Org.:
Westinghouse Savannah River Co., Aiken, SC (USA)
Sponsoring Org.:
DOE/DP
OSTI Identifier:
6396692
Report Number(s):
WSRC-RP-89-1405; CONF-900917-28
ON: DE91004257; TRN: 90-037674
DOE Contract Number:  
AC09-89SR18035
Resource Type:
Conference
Resource Relation:
Conference: American Nuclear Society topical meeting on safety of non-commercial nuclear reactor research and irradiation facilities, Boise, ID (USA), 30 Sep - 3 Oct 1990
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; HEAVY WATER COOLED REACTORS; RISK ASSESSMENT; PRODUCTION REACTORS; SAVANNAH RIVER PLANT; FAILURE MODE ANALYSIS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; MELTDOWN; REACTOR SAFETY; TRANSIENTS; ACCIDENTS; ENERGY TRANSFER; FLUID MECHANICS; MECHANICS; NATIONAL ORGANIZATIONS; REACTOR ACCIDENTS; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; US AEC; US DOE; US ERDA; US ORGANIZATIONS; 220900* - Nuclear Reactor Technology- Reactor Safety; 220700 - Nuclear Reactor Technology- Plutonium & Isotope Production Reactors

Citation Formats

Tinnes, S P, Cramer, D S, Logan, V E, Topp, S V, Smith, J A, and Brandyberry, M D. Results of the Level 1 probabilistic risk assessment (PRA) of internal events for heavy water production reactors. United States: N. p., 1990. Web.
Tinnes, S P, Cramer, D S, Logan, V E, Topp, S V, Smith, J A, & Brandyberry, M D. Results of the Level 1 probabilistic risk assessment (PRA) of internal events for heavy water production reactors. United States.
Tinnes, S P, Cramer, D S, Logan, V E, Topp, S V, Smith, J A, and Brandyberry, M D. 1990. "Results of the Level 1 probabilistic risk assessment (PRA) of internal events for heavy water production reactors". United States. https://www.osti.gov/servlets/purl/6396692.
@article{osti_6396692,
title = {Results of the Level 1 probabilistic risk assessment (PRA) of internal events for heavy water production reactors},
author = {Tinnes, S P and Cramer, D S and Logan, V E and Topp, S V and Smith, J A and Brandyberry, M D},
abstractNote = {A full-scope probabilistic risk assessment (PRA) is being performed for the Savannah River site (SRS) production reactors. The Level 1 PRA for the K Reactor has been completed and includes the assessment of reactor systems response to accidents and estimates of the severe core melt frequency (SCMF). The internal events spectrum includes those events related directly to plant systems and safety functions for which transients or failures may initiate an accident. The SRS PRA has three principal objectives: improved understanding of SRS reactor safety issues through discovery and understanding of the mechanisms involved. Improved risk management capability through tools for assessing the safety impact of both current standard operations and proposed revisions. A quantitative measure of the risks posed by SRS reactor operation to employees and the general public, to allow comparison with declared goals and other societal risks.},
doi = {},
url = {https://www.osti.gov/biblio/6396692}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Jan 01 00:00:00 EST 1990},
month = {Mon Jan 01 00:00:00 EST 1990}
}

Conference:
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