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- W20049063 abstract "The US Department of Energy is presently scheduled to begin transport of spent fuel from utility reactor sites to a federal storage facility in 1998, using casks certified by the US Nuclear Regulatory Commission. Maximizing the capacity of transport casks now being designed is essential to reduce costs and to maintain public and occupational risks ``as low as reasonably achievable``. The spent fuel to be transported in the immediate future has been cooled for a decade or more, and its radiation output is greatly reduced due to natural radioactive decay. The reduced requirements for heat dissipation and radiation shielding allow more spent fuel to be loaded into a cask of a fixed gross weight. Conceptually, cask capacity can be increased to the point where, under certain conditions, nuclear criticality safety must be considered in the design of transport casks. The reduced reactivity of the ``burned up`` fuel permits about twice as many spent assemblies to be safely transported in each cask as could be accommodated if the assemblies were fresh, unburned fuel. The criticality of the loaded, flooded cask can be calculated from three parameters which are cataloged at the reactor for each assembly. The three factors are: initial enrichment,more » usually expressed as weight percent U235; burnup and the cooling time. Casks designed taking advantage of the reduced reactivity of the burned fuel to calculate criticality are called ``burnup credit`` casks. This report discusses the burnup verification measurements for spent fuels.« less" @default.
- W20049063 created "2016-06-24" @default.
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- W20049063 date "1992-09-01" @default.
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- W20049063 title "Burnup verification measurements for spent nuclear fuel" @default.
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