Carbon-14 in waste packages for spent fuel in a tuff repository

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Description

Carbon-14 is produced naturally by cosmic ray neutrons in the upper atmosphere. It is also produced in nuclear reactors, in amounts much smaller than the global inventory. About one-third of this is released directly to the atmosphere, and the other two-thirds remains in the spent fuel. Both the Environmental Protection Agency and the Nuclear Regulatory Commission have established limits on release of the {sup 14}C in spent fuel. This is of particular concern for the proposed repository in tuff, because of the unsaturated conditions and the consequent possibility of gaseous transport of {sup 14}C as CO{sub 2}. Existing measurements and ... continued below

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14 p.

Creation Information

Van Konynenburg, R.A.; Smith, C.F.; Culham, H.W. & Smith, H.D. October 14, 1986.

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Description

Carbon-14 is produced naturally by cosmic ray neutrons in the upper atmosphere. It is also produced in nuclear reactors, in amounts much smaller than the global inventory. About one-third of this is released directly to the atmosphere, and the other two-thirds remains in the spent fuel. Both the Environmental Protection Agency and the Nuclear Regulatory Commission have established limits on release of the {sup 14}C in spent fuel. This is of particular concern for the proposed repository in tuff, because of the unsaturated conditions and the consequent possibility of gaseous transport of {sup 14}C as CO{sub 2}. Existing measurements and calculations of the {sup 14}C inventory in spent fuel are reviewed. The physical distribution and chemical forms of the {sup 14}C are discussed. Available data on the release of {sup 14}C from spent fuel in aqueous solutions and in gaseous environments of air, nitrogen, and helium are reviewed. Projected {sup 14}C behavior in a tuff repository is described. It is concluded that {sup 14}C release measurements from spent fuel into moist air at temperatures both above and below the in situ boiling point of water as well as detailed transport calculations for the tuff geological environment will be needed to determine whether the 10CFR60 and 40CFR191 requirements can be met. 56 refs., 1 tab.

Physical Description

14 p.

Notes

NTIS, PC A02/MF A01; OSTI as DE87004365

Source

  • Materials Research Society (MRS) fall meeting, Boston, MA (United States), 1-5 Dec 1986

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  • Other: DE87004365
  • Report No.: UCRL--94708
  • Report No.: CONF-861207--31
  • Grant Number: W-7405-ENG-48
  • DOI: 10.2172/59998 | External Link
  • Office of Scientific & Technical Information Report Number: 59998
  • Archival Resource Key: ark:/67531/metadc691679

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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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Creation Date

  • October 14, 1986

Added to The UNT Digital Library

  • Aug. 14, 2015, 8:43 a.m.

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  • May 31, 2016, 6:17 p.m.

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Van Konynenburg, R.A.; Smith, C.F.; Culham, H.W. & Smith, H.D. Carbon-14 in waste packages for spent fuel in a tuff repository, report, October 14, 1986; California. (digital.library.unt.edu/ark:/67531/metadc691679/: accessed November 21, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.