A fuel response model for the design of spent fuel shipping casks

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Description

The radiological source terms pertinent to spent fuel shipping cask safety assessments are of three distinct origins. One of these concerns residual contamination within the cask due to handling operations and previous shipments. A second is associated with debris (''crud'') that had been deposited on the fuel rods in the course of reactor operation, and a third involves the radioactive material contained within the rods. Although the lattermost source of radiotoxic material overwhelms the others in terms of inventory, its release into the shipping cask, and thence into the biosphere, requires the breach of an additional release barrier, viz., the ... continued below

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Pages: 11

Creation Information

Malinauskas, A. P.; Duffey, T. A.; Einziger, R. E.; Hobbins, R. R.; Jordon, H.; Rashid, Y. R. et al. January 1, 1989.

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Description

The radiological source terms pertinent to spent fuel shipping cask safety assessments are of three distinct origins. One of these concerns residual contamination within the cask due to handling operations and previous shipments. A second is associated with debris (''crud'') that had been deposited on the fuel rods in the course of reactor operation, and a third involves the radioactive material contained within the rods. Although the lattermost source of radiotoxic material overwhelms the others in terms of inventory, its release into the shipping cask, and thence into the biosphere, requires the breach of an additional release barrier, viz., the fuel rod cladding. Hence, except for the special case involving the transport of fuel rods containing previously breached claddings, considerations of the source terms due to material contained in the fuel rods are complicated by the need to address the likelihood of fuel cladding failure during transport. The purpose of this report is to describe a methodology for estimating the shipping cask source terms contribution due to radioactive material contained within the spent fuel rods. Thus, the probability of fuel cladding failure as well as radioactivity release is addressed. 8 refs., 2 tabs.

Physical Description

Pages: 11

Notes

NTIS, PC A03/MF A01 - OSTI; 1.

Source

  • International symposium on packaging and transporting of radioactive materials, Washington, DC, USA, 11 Jun 1989

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  • Other: DE89013544
  • Report No.: CONF-890631-45
  • Grant Number: AC04-76DP00789
  • Grant Number: AC05-84OR21400
  • Grant Number: AC06-76RL01830
  • Grant Number: AC07-76ID01570
  • Office of Scientific & Technical Information Report Number: 6020112
  • Archival Resource Key: ark:/67531/metadc1098889

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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.

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  • January 1, 1989

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  • Feb. 18, 2018, 3:59 p.m.

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  • April 23, 2018, 1:09 p.m.

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Malinauskas, A. P.; Duffey, T. A.; Einziger, R. E.; Hobbins, R. R.; Jordon, H.; Rashid, Y. R. et al. A fuel response model for the design of spent fuel shipping casks, article, January 1, 1989; Albuquerque, New Mexico. (digital.library.unt.edu/ark:/67531/metadc1098889/: accessed May 25, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.