Response of spent LWR fuel to extreme environments

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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. ... continued below

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Pages: 8

Creation Information

Sandoval, R.P.; Burian, R.J.; Kok, K.D.; DiSalvo, R.; Balmert, M.E.; Freeman-Kelly, R. et al. January 1, 1986.

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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

Notes

NTIS, PC A02/MF A01; 1.

Source

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

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  • 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

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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

  • January 1, 1986

Added to The UNT Digital Library

  • Feb. 10, 2018, 10:06 p.m.

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  • April 20, 2018, 11:37 a.m.

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Sandoval, R.P.; Burian, R.J.; Kok, K.D.; DiSalvo, R.; Balmert, M.E.; Freeman-Kelly, R. et al. Response of spent LWR fuel to extreme environments, article, January 1, 1986; United States. (digital.library.unt.edu/ark:/67531/metadc1092671/: accessed November 16, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.