Equations for predicting release rates for waste packages in unsaturated tuff

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Nuclear waste will be placed in the potential repository at Yucca Mountain in waste packages. Spent fuel assemblies or consolidated fuel rods and borosilicate glass in steel pour canisters will be enclosed in sealed containers. The waste package consists of the waste form, the cladding on spent fuel or the defense-waste pour canister, and the outside container. Current design calls for the waste packages to be surrounded by an air gap. Although the waste package is generally not seen as the primary barrier for nuclear waste isolation it must in fact meet specific regulatory requirements: substantially complete requirement and release-rate ... continued below

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25 p.

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Sadeghi, M.M.; Pigford, T.H.; Chambre, P.L. & Lee, W.W.L. August 1, 1990.

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Description

Nuclear waste will be placed in the potential repository at Yucca Mountain in waste packages. Spent fuel assemblies or consolidated fuel rods and borosilicate glass in steel pour canisters will be enclosed in sealed containers. The waste package consists of the waste form, the cladding on spent fuel or the defense-waste pour canister, and the outside container. Current design calls for the waste packages to be surrounded by an air gap. Although the waste package is generally not seen as the primary barrier for nuclear waste isolation it must in fact meet specific regulatory requirements: substantially complete requirement and release-rate from the engineered barrier system [USNRC 1983]. This report gives derivations of equations for predicting releases rates. We consider the release of three types of species: solubility-limited species, species released congruent with solid-solid alteration of spent-fuel matrix or borosilicate glass, and readily soluble species from the fuel-cladding gap, gas plenum, and readily accessible grain boundaries. We develop analytic expressions for the release rates of individual constituents from each of these mechanisms. For a given species and for given parameters, the mechanism that results in the lowest predicted release rate is to be adopted as the rate-controlling mechanism for that species. Some of the equations are newly derived for this report, others are restated from earlier work. Release rates have been calculated for key radionuclides in a companion report. 11 refs., 7 figs.

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25 p.

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INIS; OSTI as DE91010212

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  • Other Information: PBD: Aug 1990

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  • Other: DE91010212
  • Report No.: LBL--29254
  • Grant Number: AC03-76SF00098
  • DOI: 10.2172/138055 | External Link
  • Office of Scientific & Technical Information Report Number: 138055
  • Archival Resource Key: ark:/67531/metadc619059

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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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  • August 1, 1990

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  • June 16, 2015, 7:43 a.m.

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  • April 5, 2016, 12:26 p.m.

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Sadeghi, M.M.; Pigford, T.H.; Chambre, P.L. & Lee, W.W.L. Equations for predicting release rates for waste packages in unsaturated tuff, report, August 1, 1990; California. (digital.library.unt.edu/ark:/67531/metadc619059/: accessed December 18, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.