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S.M. Frank; D. D. Keiser, Jr.; K. C. Marsden
Idaho National Laboratory INL (United States). Funding organisation: DOE - NE (United States)2007
Idaho National Laboratory INL (United States). Funding organisation: DOE - NE (United States)2007
AbstractAbstract
[en] Fission-product technetium accumulated during treatment of spent nuclear fuel will ultimately be disposed of in a geological repository. The exact form of Tc for disposal has yet to be determined; however, a reasonable solution is to incorporate elemental Tc into a metallic waste form similar to the waste form produced during the pyrochemical treatment of spent, sodium-bonded fuel. This metal waste form, produced at the Idaho National Laboratory, has undergone extensive qualification examination and testing for acceptance to the Yucca Mountain geological repository. It is from this extensive qualification effort that the behavior of Tc and other fission products in the waste form has been elucidated, and that the metal waste form is extremely robust in the retention of fission products, such as Tc, in repository like conditions. This manuscript will describe the metal waste form, the behavior of Tc in the waste form; and current research aimed at determining the maximum possible loading of Tc into the metal waste and subsequent determination of the performance of high Tc loaded metal waste forms
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1 Sep 2007; vp; Global 2007: Advanced Nuclear Fuel Cycles and Systems; Boise, ID (United States); 9-13 Sep 2007; AC07-99ID-13727; Available from http://www.inl.gov/technicalpublications/Documents/3792228.pdf; PURL: https://www.osti.gov/servlets/purl/918181-luMs8C/
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