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Title: Loss of DHR sequences at Browns Ferry Unit One - accident-sequence analysis

Abstract

This study describes the predicted response of Unit One at the Browns Ferry Nuclear Plant to a postulated loss of decay heat removal (DHR) capability following scram from full power with the power conversion system unavailable. In accident sequences without DHR capability, the residual heat removal (RHR) system functions of pressure suppression pool cooling and reactor vessel shutdown cooling are unavailable. Consequently, all decay heat energy is stored in the pressure suppression pool with a concomitant increase in pool temperature and primary containment pressure. With the assumption that DHR capability is not regained during the lengthy course of this accident sequence, the containment ultimately fails by overpressurization. Although unlikely, this catastrophic failure might lead to loss of the ability to inject cooling water into the reactor vessel, causing subsequent core uncovery and meltdown. The timing of these events and the effective mitigating actions that might be taken by the operator are discussed in this report.

Authors:
; ; ;
Publication Date:
Research Org.:
Oak Ridge National Lab., TN (USA)
OSTI Identifier:
6168063
Report Number(s):
NUREG/CR-2973; ORNL/TM-8532
ON: DE83012314
DOE Contract Number:  
W-7405-ENG-26
Resource Type:
Technical Report
Resource Relation:
Other Information: Portions are illegible in microfiche products
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BROWNS FERRY-1 REACTOR; REACTOR ACCIDENTS; RHR SYSTEMS; AFTER-HEAT REMOVAL; COMPUTER CALCULATIONS; CONTAINMENT SYSTEMS; FAILURES; HEAT TRANSFER; HYDRAULICS; PRESSURE GRADIENTS; PRESSURE SUPPRESSION; REACTOR SAFETY; TEMPERATURE GRADIENTS; ACCIDENTS; BWR TYPE REACTORS; CONTAINMENT; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; MECHANICS; MIXED SPECTRUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; REMOVAL; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210100 - Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled

Citation Formats

Cook, D.H., Grene, S.R., Harrington, R.M., and Hodge, S.A. Loss of DHR sequences at Browns Ferry Unit One - accident-sequence analysis. United States: N. p., 1983. Web.
Cook, D.H., Grene, S.R., Harrington, R.M., & Hodge, S.A. Loss of DHR sequences at Browns Ferry Unit One - accident-sequence analysis. United States.
Cook, D.H., Grene, S.R., Harrington, R.M., and Hodge, S.A. Sun . "Loss of DHR sequences at Browns Ferry Unit One - accident-sequence analysis". United States.
@article{osti_6168063,
title = {Loss of DHR sequences at Browns Ferry Unit One - accident-sequence analysis},
author = {Cook, D.H. and Grene, S.R. and Harrington, R.M. and Hodge, S.A.},
abstractNote = {This study describes the predicted response of Unit One at the Browns Ferry Nuclear Plant to a postulated loss of decay heat removal (DHR) capability following scram from full power with the power conversion system unavailable. In accident sequences without DHR capability, the residual heat removal (RHR) system functions of pressure suppression pool cooling and reactor vessel shutdown cooling are unavailable. Consequently, all decay heat energy is stored in the pressure suppression pool with a concomitant increase in pool temperature and primary containment pressure. With the assumption that DHR capability is not regained during the lengthy course of this accident sequence, the containment ultimately fails by overpressurization. Although unlikely, this catastrophic failure might lead to loss of the ability to inject cooling water into the reactor vessel, causing subsequent core uncovery and meltdown. The timing of these events and the effective mitigating actions that might be taken by the operator are discussed in this report.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1983},
month = {5}
}

Technical Report:
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