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Title: United States experience in probabilistic risk assessment for a graphite moderated, channel reactor

Abstract

The United States operated a number of graphite moderated, water cooled, pressure tube (or channel type) reactors at the Hanford Site in Washington State. The last of these reactors to operate was the Hanford N Reactor which was designed to produce steam for the generation of electricity for civilian energy use as well as special nuclear material. In 1982, a review team recommended that a probabilistic risk assessment (PRA) be conducted for the reactor. The basis for this recommendation was that the reactor represented a unique facility and therefore the safety insights gained from operations at other facilities were not directly transferable to it. Furthermore, the reactor was going through a series of upgrades and it was felt that the selection of competing improvements would benefit from a risk perspective to help judge the relative value of these upgrades. The initial Level 1 PRA was initiated just prior to the time of the Chernobyl accident in 1986. After the accident, a limited scope PRA was also conducted. The limited scope PRA was completed in July 1987. The original Level 1 PRA was brought to completion in August 1988 and was followed by complete Level 3 analyses including an evaluation ofmore » external initiating events. This paper will focus on the Level 1 effort. The objectives of the Level 1 PRA for N Reactor were: identification of the plant features that are the most important contributors to fuel-damage frequency; development of plant logic models for use in analyzing safety and reliability issues; identification of dominant accident sequences and their frequencies for input into the Level 2/3 PRA and external events analyses; and establishment of a Hanford team with demonstrable expertise in performing risk and reliability analyses.« less

Authors:
 [1];  [2]
  1. Pacific Northwest Lab., Richland, WA (US)
  2. Westinghouse Hanford Co., Richland, WA (US)
Publication Date:
Research Org.:
Pacific Northwest Lab., Richland, WA (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
10176803
Report Number(s):
PNL-SA-21788; CONF-9306189-3
ON: DE93017662; TRN: 93:018856
DOE Contract Number:  
AC06-76RL01830
Resource Type:
Conference
Resource Relation:
Conference: NE `93: 4th annual scientific and technical conference of the Nuclear Society: nuclear energy and human safety,Nizhni Novgorod (Russian Federation),28 Jun - 2 Jul 1993; Other Information: PBD: Jun 1993
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; N-REACTOR; RISK ASSESSMENT; PROBABILITY; FUEL ELEMENT FAILURE; SAFETY ANALYSIS; MATHEMATICAL MODELS; RELIABILITY; REACTOR ACCIDENTS; PERSONNEL; TRAINING; HANFORD RESERVATION; HISTORICAL ASPECTS; DATA ANALYSIS; INFORMATION SYSTEMS; REACTOR CORES; 220900; 220600; REACTOR SAFETY; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS

Citation Formats

Heaberlin, S W, and Zentner, M D. United States experience in probabilistic risk assessment for a graphite moderated, channel reactor. United States: N. p., 1993. Web.
Heaberlin, S W, & Zentner, M D. United States experience in probabilistic risk assessment for a graphite moderated, channel reactor. United States.
Heaberlin, S W, and Zentner, M D. Tue . "United States experience in probabilistic risk assessment for a graphite moderated, channel reactor". United States. https://www.osti.gov/servlets/purl/10176803.
@article{osti_10176803,
title = {United States experience in probabilistic risk assessment for a graphite moderated, channel reactor},
author = {Heaberlin, S W and Zentner, M D},
abstractNote = {The United States operated a number of graphite moderated, water cooled, pressure tube (or channel type) reactors at the Hanford Site in Washington State. The last of these reactors to operate was the Hanford N Reactor which was designed to produce steam for the generation of electricity for civilian energy use as well as special nuclear material. In 1982, a review team recommended that a probabilistic risk assessment (PRA) be conducted for the reactor. The basis for this recommendation was that the reactor represented a unique facility and therefore the safety insights gained from operations at other facilities were not directly transferable to it. Furthermore, the reactor was going through a series of upgrades and it was felt that the selection of competing improvements would benefit from a risk perspective to help judge the relative value of these upgrades. The initial Level 1 PRA was initiated just prior to the time of the Chernobyl accident in 1986. After the accident, a limited scope PRA was also conducted. The limited scope PRA was completed in July 1987. The original Level 1 PRA was brought to completion in August 1988 and was followed by complete Level 3 analyses including an evaluation of external initiating events. This paper will focus on the Level 1 effort. The objectives of the Level 1 PRA for N Reactor were: identification of the plant features that are the most important contributors to fuel-damage frequency; development of plant logic models for use in analyzing safety and reliability issues; identification of dominant accident sequences and their frequencies for input into the Level 2/3 PRA and external events analyses; and establishment of a Hanford team with demonstrable expertise in performing risk and reliability analyses.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1993},
month = {6}
}

Conference:
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