U.S. regulatory research program for implementation of burnup credit in transport casks
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2001-09-10
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Abstract:In 1999 the U.S. Nuclear Regulatory Commission (U.S. NRC) initiated a research program to
support the development of technical bases and guidance that would facilitate the implementation of
burnup credit into licensing activities for transport and dry cask storage. This paper reviews the
following major areas of investigation: (1) specification of axial burnup profiles, (2) assumption on
cooling time, (3) allowance for assemblies with fixed and removable neutron absorbers, (4) the need
for a burnup margin for fuel with initial enrichments over 4 wt %, and (5) evaluation of assay data
and critical experiments. The capabilities of a new computational tool that facilitates the
performance and coupling of the depletion and criticality analyses needed for burnup credit are also
discussed.
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