Transforming criticality control methods for EBR-II fuel handling during reactor decommissioning

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Description

A review of the Department of Energy (DOE) request to decommission the Experimental Breeder Reactor-II (EBR-II) was conducted in order to develop a scope of work and analysis method for performing the safety review of the facility. Evaluation of the current national standards, DOE orders, EBR-II nuclear safeguards and criticality control practices showed that a decommissioning policy for maintaining criticality safety during a long term fuel transfer process did not exist. The purpose of this research was to provide a technical basis for transforming the reactor from an instrumentation and measurement controlled system to a system that provides both physical ... continued below

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10 p.

Creation Information

Eberle, C.S.; Dean, E.M. & Angelo, P.L. December 31, 1995.

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  • Argonne National Laboratory
    Publisher Info: Argonne National Lab., Idaho Falls, ID (United States)
    Place of Publication: Idaho Falls, Idaho

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Description

A review of the Department of Energy (DOE) request to decommission the Experimental Breeder Reactor-II (EBR-II) was conducted in order to develop a scope of work and analysis method for performing the safety review of the facility. Evaluation of the current national standards, DOE orders, EBR-II nuclear safeguards and criticality control practices showed that a decommissioning policy for maintaining criticality safety during a long term fuel transfer process did not exist. The purpose of this research was to provide a technical basis for transforming the reactor from an instrumentation and measurement controlled system to a system that provides both physical constraint and administrative controls to prevent criticality accidents. Essentially, this was done by modifying the reactor core configuration, reactor operations procedures and system instrumentation to meet the safety practices of ANS-8.1-1983. Subcritical limits were determined by applying established liquid metal reactor methods for both the experimental and computational validations.

Physical Description

10 p.

Notes

INIS; OSTI as DE97000684

Source

  • 5. international conference on nuclear criticality safety, Albuquerque, NM (United States), 17-22 Sep 1995

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  • Other: DE97000684
  • Report No.: ANL/ED/CP--85397
  • Report No.: CONF-9509100--40
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 435199
  • Archival Resource Key: ark:/67531/metadc683766

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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Creation Date

  • December 31, 1995

Added to The UNT Digital Library

  • July 25, 2015, 2:20 a.m.

Description Last Updated

  • May 16, 2016, 6:09 p.m.

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Eberle, C.S.; Dean, E.M. & Angelo, P.L. Transforming criticality control methods for EBR-II fuel handling during reactor decommissioning, article, December 31, 1995; Idaho Falls, Idaho. (digital.library.unt.edu/ark:/67531/metadc683766/: accessed April 24, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.