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

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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.

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

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This article is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 14 times . More information about this article can be viewed below.

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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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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.

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10 p.

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INIS; OSTI as DE97000684

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  • 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

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  • December 31, 1995

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  • July 25, 2015, 2:20 a.m.

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  • 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 February 23, 2019), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.