Response of spent LWR fuel to extreme environments Metadata

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Title

  • Main Title Response of spent LWR fuel to extreme environments

Creator

  • Author: Sandoval, R.P.
    Creator Type: Personal
  • Author: Burian, R.J.
    Creator Type: Personal
  • Author: Kok, K.D.
    Creator Type: Personal
  • Author: DiSalvo, R.
    Creator Type: Personal
  • Author: Balmert, M.E.
    Creator Type: Personal
  • Author: Freeman-Kelly, R.
    Creator Type: Personal
  • Author: Fentiman, A.W.
    Creator Type: Personal

Publisher

  • Name: Sandia National Labs., Albuquerque, NM (USA)
    Place of Publication: United States
  • Name: Battelle Columbus Labs., OH (USA)
    Place of Publication: United States

Date

  • Creation: 1986-01-01

Language

  • English

Description

  • Content Description: The research reported in this paper addresses the radiological source term which could arise when irradiated fuel in transport from a commercial light water reactor is exposed to the extreme environments postulated for some transportation accidents, specifically those involving a fire. The release of spent fuel radionuclides to the environment requires a breach of both the cask and the fuel rod cladding. Past research has given significant emphasis to evaluating the response of the shipping cask to mechanical and/or thermal loads from hypothetical accidents. Less consideration has been given to evaluating the response of the fuel rods to these environments. In this paper, the response of the fuel rods to an extreme thermal event was experimentally evaluated and the quantity of solid fuel material that could be released from the fuel rods to the cask cavity was estimated. Briefly, the objectives of this study were as follows: (1) Identify those conditions within a transportation cask which might produce fuel-rod cladding failure, emphasizing conditions associated with fires, and (2) Determine by experiment and analysis the nature of the source term so produced. The release of radionuclides from coolant or deposits on the outer surfaces of the fuel assembly was not addressed in this study. 6 figs., 2 figs.
  • Physical Description: Pages: 8

Subject

  • Keyword: Fuels
  • Keyword: Source Terms
  • Keyword: Testing 420204* -- Engineering-- Shipping Containers
  • Keyword: Spent Fuel Casks
  • Keyword: After-Heat
  • Keyword: International Organizations
  • Keyword: Particles
  • Keyword: Particulates
  • Keyword: Water Cooled Reactors
  • Keyword: Transport
  • Keyword: Materials
  • Keyword: Failures
  • Keyword: Reactor Materials
  • Keyword: Fission Product Release
  • Keyword: Accidents
  • STI Subject Categories: 050900 -- Nuclear Fuels-- Transport, Handling, & Storage
  • Keyword: Reactors
  • Keyword: Burnup
  • Keyword: Mechanical Properties
  • Keyword: Casks
  • Keyword: Temperature Effects
  • Keyword: Swelling
  • STI Subject Categories: 11 Nuclear Fuel Cycle And Fuel Materials
  • Keyword: Fires
  • Keyword: Nuclear Fuels
  • Keyword: Creep
  • Keyword: Energy Sources
  • Keyword: Iaea
  • STI Subject Categories: 42 Engineering
  • Keyword: Ruptures
  • Keyword: Performance Testing
  • Keyword: Spent Fuels
  • Keyword: Containers

Source

  • Conference: International symposium on the packaging and transport of radioactive materials (PATRAM '86), Davos, Switzerland, 16 Jun 1986

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: DE86011648
  • Report No.: SAND-85-2208C
  • Report No.: IAEA-SM-286/92
  • Report No.: CONF-860604-23
  • Grant Number: AC04-76DP00789
  • Office of Scientific & Technical Information Report Number: 5720635
  • Archival Resource Key: ark:/67531/metadc1092671

Note

  • Display Note: NTIS, PC A02/MF A01; 1.