Impact of emergency operating instructions on severe-accident sequences. [BWR] Metadata

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Title

  • Main Title Impact of emergency operating instructions on severe-accident sequences. [BWR]

Creator

  • Author: Tzanos, C.P.
    Creator Type: Personal

Publisher

  • Name: Argonne National Laboratory
    Place of Publication: Illinois

Date

  • Creation: 1983-01-01

Language

  • English

Description

  • Content Description: This work presents a quantitative assessment of the impact that the emergency operating instructions (EOIs) of operating nuclear power plants may have on the frequency of severe accident sequences. Frequencies of such sequences were calculated based on the operator actions required by the EOIs of a reference BWR plant and compared to those resulting from an optimized set of instructions. The optimized set of EOIs was based on the necessary operator actions indicated by analyses of the Severe Accident Sequence Analysis (SASA) program. The impact of the EOIs is expected to be especially significant in sequences where the available time for operator response is short. For this reason, in this comparison three sequences were considered: loss of the high pressure injection systems (HCPI and RCIC) with the power conversion system (PCS) unavailable; loss of offsite power; and station blackout.
  • Physical Description: Pages: 5

Subject

  • Keyword: Water Cooled Reactors
  • Keyword: Bwr Type Reactors
  • Keyword: Reactor Operators
  • Keyword: Emergency Plans
  • Keyword: Human Factors
  • Keyword: Personnel
  • Keyword: Reactor Safety
  • STI Subject Categories: 210100 -- Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled
  • Keyword: Accidents
  • STI Subject Categories: 22 General Studies Of Nuclear Reactors
  • Keyword: Engineering
  • Keyword: Reactor Accidents
  • Keyword: Reactor Control Systems
  • Keyword: Human Factors Engineering
  • Keyword: Reactors
  • STI Subject Categories: 21 Specific Nuclear Reactors And Associated Plants
  • Keyword: Control Systems
  • Keyword: Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety
  • Keyword: Safety

Source

  • Conference: American Nuclear Society winter meeting, San Francisco, CA, USA, 30 Oct 1983

Collection

  • Name: Office of Scientific & Technical Information Technical Reports
    Code: OSTI

Institution

  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Article

Format

  • Text

Identifier

  • Other: DE83015460
  • Report No.: CONF-831047-41
  • Grant Number: W-31-109-ENG-38
  • Office of Scientific & Technical Information Report Number: 5701369
  • Archival Resource Key: ark:/67531/metadc1092178

Note

  • Display Note: NTIS, PC A02/MF A01.