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Title: Containment venting as a mitigation technique for BWR Mark I plant ATWS

Abstract

Containment venting is studied as a mitigation strategy for preventing or delaying severe fuel damage following hypothetical BWR Anticipated Transient Without SCRAM (ATWS) accidents initiated by MSIV-closure, and compounded by failure of the Standby Liquid Control (SLC) system injection of sodium pentaborate solution and by the failure of manually initiated control rod insertion. The venting of primary containment after reaching 75 psia (0.52 MPa) is found to result in the release of the vented steam inside the reactor building, and to result in inadequate Net Positive Suction Head (NPSH) for any system pumping from the pressure suppression pool. CONTAIN code calculations show that personnel access to large portions of the reactor building would be lost soon after the initiation of venting and that the temperatures reached would be likely to result in independent equipment failures. It is concluded that containment venting would be more likely to cause or to hasten the onset of severe fuel damage than to prevent or to delay it.

Authors:
Publication Date:
Research Org.:
Oak Ridge National Lab., TN (USA)
OSTI Identifier:
7047577
Report Number(s):
CONF-8610135-9
ON: DE87002179
DOE Contract Number:  
AC05-84OR21400
Resource Type:
Conference
Resource Relation:
Conference: 14. water reactor safety information meeting, Gaithersburg, MD, USA, 27 Oct 1986; Other Information: Paper copy only, copy does not permit microfiche production
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; ATWS; CONTAINMENT SYSTEMS; BUILDINGS; HEAT TRANSFER; HYDRAULICS; REACTOR VESSELS; VENTILATION; ACCIDENTS; CONTAINERS; CONTAINMENT; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; FLUID MECHANICS; MECHANICS; REACTOR ACCIDENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210100 - Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled

Citation Formats

Harrington, R M. Containment venting as a mitigation technique for BWR Mark I plant ATWS. United States: N. p., 1986. Web.
Harrington, R M. Containment venting as a mitigation technique for BWR Mark I plant ATWS. United States.
Harrington, R M. Wed . "Containment venting as a mitigation technique for BWR Mark I plant ATWS". United States. https://www.osti.gov/servlets/purl/7047577.
@article{osti_7047577,
title = {Containment venting as a mitigation technique for BWR Mark I plant ATWS},
author = {Harrington, R M},
abstractNote = {Containment venting is studied as a mitigation strategy for preventing or delaying severe fuel damage following hypothetical BWR Anticipated Transient Without SCRAM (ATWS) accidents initiated by MSIV-closure, and compounded by failure of the Standby Liquid Control (SLC) system injection of sodium pentaborate solution and by the failure of manually initiated control rod insertion. The venting of primary containment after reaching 75 psia (0.52 MPa) is found to result in the release of the vented steam inside the reactor building, and to result in inadequate Net Positive Suction Head (NPSH) for any system pumping from the pressure suppression pool. CONTAIN code calculations show that personnel access to large portions of the reactor building would be lost soon after the initiation of venting and that the temperatures reached would be likely to result in independent equipment failures. It is concluded that containment venting would be more likely to cause or to hasten the onset of severe fuel damage than to prevent or to delay it.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1986},
month = {1}
}

Conference:
Other availability
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