An analysis of plutonium immobilization versus the "spent fuel" standard Metadata

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Title

  • Main Title An analysis of plutonium immobilization versus the "spent fuel" standard

Creator

  • Author: Gray, W. L.
    Creator Type: Personal
  • Author: McKibben, J. M.
    Creator Type: Personal

Contributor

  • Sponsor: United States. Department of Energy. Office of the Assistant Secretary for Defense Programs.
    Contributor Type: Organization
    Contributor Info: USDOE Office of Defense Programs (DP)

Publisher

  • Name: Lawrence Livermore National Laboratory
    Place of Publication: Livermore, California
    Additional Info: Lawrence Livermore National Laboratory, Livermore, CA

Date

  • Creation: 1998-06-16

Language

  • English

Description

  • Content Description: Safe Pu management is an important and urgent task with profound environmental, national, and international security implications. Presidential Policy Directive 13 and analyses by scientific, technical, and international policy organizations brought about a focused effort within the Department of Energy (DOE) to identify and implement long-term disposition paths for surplus Pu. The principal goal is to render surplus Pu as inaccessible and unattractive for reuse in nuclear weapons as Pu in spent reactor fuel. In the Programmatic Environmental Impact Statement and Record of Decision for the Storage and Disposition of Weapons- Usable Fissile Materials (1997), DOE announced pursuit of two disposition technologies: (1) irradiation of Pu as MOX fuel in existing reactors and (2) immobilization of Pu into solid forms containing fission products as a radiation barrier. DOE chose an immobilization approach that includes �use of the can-in-canister option.. . for a portion of the surplus, non-pit Pu material.� In the can-in-canister approach, cans of glass or ceramic forms containing Pu are encapsulated within canisters of HLW glass. In support of the selection process, a technical evaluation of retrievability and recoverability of Pu from glass and ceramic forms by a host nation and by rogue nations or subnational groups was completed. The evaluation involved determining processes and flowsheets for Pu recovery, comparing these processes against criteria and metrics established by the Fissile Materials Disposition Program and then comparing the recovery processes against each other and against SNF processes.
  • Physical Description: 1.6 Megabytes

Subject

  • Keyword: Storage
  • STI Subject Categories: 05 Nuclear Fuels
  • Keyword: Plutonium
  • Keyword: Spent Fuels

Source

  • Conference: American Nuclear Society Third Topical Meeting, Charleston, SC, September 8-11, 1998

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: DE00003578
  • Report No.: UCRL-JC-131529
  • Grant Number: W-7405-Eng-48
  • Office of Scientific & Technical Information Report Number: 3578
  • Archival Resource Key: ark:/67531/metadc676555
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