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Title: Proceedings of the US Nuclear Regulatory Commission nineteenth water reactor safety information meeting. Volume 3, Structural engineering; advanced reactor research; advanced passive reactors; human factors research; human factors issues related to advanced passive LWRs; thermal hydraulics; earth sciences: Addendum

Abstract

Following the unexpected, but safely terminated, power and flow oscillations in the LaSalle-2 Boiling Water Reactor (BWR) on March 9, 1988, the Nuclear Regulatory Commission (NRC) Offices of Nuclear Reactor Regulation (NRR) and of Analysis and Evaluation of Operational Data (AEOD) requested that the Office of Nuclear Regulation Research (RES) carry out BWR stability analyses, centered around fourteen specific questions. The questions are motivated by the demand to meet the General Design Criterion 12 in Appendix A of the Code of Federal Regulation 10CFR50, which requires that reactor power oscillations violating Technical Specifications be either impossible by design, or detected and suppressed. Ten of the fourteen questions address BWR stability issues in general and are dealt with in this paper. The other four questions address local, out-of-phase oscillations and matters of instrumentation; they fall outside the scope of the work reported here.

Authors:
 [1]
  1. comp.; Brookhaven National Lab., Upton, NY (United States)
Publication Date:
Research Org.:
Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; Brookhaven National Lab., Upton, NY (United States)
Sponsoring Org.:
Nuclear Regulatory Commission, Washington, DC (United States)
OSTI Identifier:
10162029
Report Number(s):
NUREG/CP-0119-Vol.3-Add.; CONF-911079-Vol.3-Add.
ON: TI92017176
Resource Type:
Conference
Resource Relation:
Conference: 19. Nuclear Regulatory Commission (NRC) water reactor safety information meeting,Bethesda, MD (United States),28-30 Oct 1991; Other Information: PBD: Jun 1992
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; STABILITY; EXCURSIONS; LA SALLE COUNTY-2 REACTOR; SCRAM; REACTOR SAFETY; ATWS; FLUID FLOW; OSCILLATIONS; TRANSIENTS; FAILURE MODE ANALYSIS; 220900; 210100; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, BOILING WATER COOLED

Citation Formats

Weiss, A J. Proceedings of the US Nuclear Regulatory Commission nineteenth water reactor safety information meeting. Volume 3, Structural engineering; advanced reactor research; advanced passive reactors; human factors research; human factors issues related to advanced passive LWRs; thermal hydraulics; earth sciences: Addendum. United States: N. p., 1992. Web.
Weiss, A J. Proceedings of the US Nuclear Regulatory Commission nineteenth water reactor safety information meeting. Volume 3, Structural engineering; advanced reactor research; advanced passive reactors; human factors research; human factors issues related to advanced passive LWRs; thermal hydraulics; earth sciences: Addendum. United States.
Weiss, A J. 1992. "Proceedings of the US Nuclear Regulatory Commission nineteenth water reactor safety information meeting. Volume 3, Structural engineering; advanced reactor research; advanced passive reactors; human factors research; human factors issues related to advanced passive LWRs; thermal hydraulics; earth sciences: Addendum". United States.
@article{osti_10162029,
title = {Proceedings of the US Nuclear Regulatory Commission nineteenth water reactor safety information meeting. Volume 3, Structural engineering; advanced reactor research; advanced passive reactors; human factors research; human factors issues related to advanced passive LWRs; thermal hydraulics; earth sciences: Addendum},
author = {Weiss, A J},
abstractNote = {Following the unexpected, but safely terminated, power and flow oscillations in the LaSalle-2 Boiling Water Reactor (BWR) on March 9, 1988, the Nuclear Regulatory Commission (NRC) Offices of Nuclear Reactor Regulation (NRR) and of Analysis and Evaluation of Operational Data (AEOD) requested that the Office of Nuclear Regulation Research (RES) carry out BWR stability analyses, centered around fourteen specific questions. The questions are motivated by the demand to meet the General Design Criterion 12 in Appendix A of the Code of Federal Regulation 10CFR50, which requires that reactor power oscillations violating Technical Specifications be either impossible by design, or detected and suppressed. Ten of the fourteen questions address BWR stability issues in general and are dealt with in this paper. The other four questions address local, out-of-phase oscillations and matters of instrumentation; they fall outside the scope of the work reported here.},
doi = {},
url = {https://www.osti.gov/biblio/10162029}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Jun 01 00:00:00 EDT 1992},
month = {Mon Jun 01 00:00:00 EDT 1992}
}

Conference:
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