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

Thumbnail image of item number 1 in: 'Transforming criticality control methods for EBR-II fuel handling during reactor decommissioning'.
Thumbnail image of item number 2 in: 'Transforming criticality control methods for EBR-II fuel handling during reactor decommissioning'.
Thumbnail image of item number 3 in: 'Transforming criticality control methods for EBR-II fuel handling during reactor decommissioning'.
Thumbnail image of item number 4 in: 'Transforming criticality control methods for EBR-II fuel handling during reactor decommissioning'.
Showing 1-4 of 10 pages in this article.

PDF Version Also Available for Download.

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

Physical Description

10 p.

Creation Information

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

Context

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 12 times . More information about this article can be viewed below.

Who

People and organizations associated with either the creation of this article or its content.

Authors

Sponsor

Publisher

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

Provided By

UNT Libraries Government Documents Department

Serving as both a federal and a state depository library, the UNT Libraries Government Documents Department maintains millions of items in a variety of formats. The department is a member of the FDLP Content Partnerships Program and an Affiliated Archive of the National Archives.

About | Browse this Partner

Contact Us

Corrections Questions

What

Descriptive information to help identify this article. Follow the links below to find similar items on the Digital Library.

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

Language

Item Type

Identifier

Unique identifying numbers for this article in the Digital Library or other systems.

  • 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

Collections

This article is part of the following collection of related materials.

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.

About | Browse this Collection

What responsibilities do I have when using this article?

Digital Files

When

Dates and time periods associated with this article.

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.

Usage Statistics

When was this article last used?

Yesterday: 0
Past 30 days: 1
Total Uses: 12
More Statistics

Interact With This Article

Here are some suggestions for what to do next.

Start Reading

Thumbnail image of item number 1 in: 'Transforming criticality control methods for EBR-II fuel handling during reactor decommissioning'.
Thumbnail image of item number 2 in: 'Transforming criticality control methods for EBR-II fuel handling during reactor decommissioning'.
Thumbnail image of item number 3 in: 'Transforming criticality control methods for EBR-II fuel handling during reactor decommissioning'.
Thumbnail image of item number 4 in: 'Transforming criticality control methods for EBR-II fuel handling during reactor decommissioning'.

PDF Version Also Available for Download.

Citations, Rights, Re-Use

International Image Interoperability Framework

IIF Logo

We support the IIIF Presentation API

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 November 13, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.