U.S. regulatory research program for implementation of burnup credit in transport casks

Details

• Creators:
  Parks, C. V. ; Wagner, J. C. ; Gauld, I. C. ; Broadhead, B. L. ; Sanders, C. E.
• Corporate Contributors:
  Oak Ridge National Laboratory
• Subject/TRT Terms:
  • Casks
  • Nuclear reactor components
  • Nuclear reactor coolants
  • Burnup
  • Criticality
  • Implementation
  • Neutron absorbers
  • Packaging
  • Radioactive materials
  • Regulations
  More +
• Publication/ Report Number:
  P01-111795
• Resource Type:
  Proceedings
• Geographical Coverage:
  United States
• Corporate Publisher:
  Oak Ridge National Laboratory
• 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.
• Format:
  PDF
• Download URL:
  https://rosap.ntl.bts.gov/view/dot/15287/dot_15287_DS1.pdf
• File Type:
  [PDF - 255.19 KB]
• Collection(s):
  US Transportation Collection
• Main Document Checksum:
  urn:sha-512:6c8fa17b0b4efa80dfdeaf7614236300d4bfec09b878705bb4df6ccd0c99ca618a1ca34bd7925c0e84e3b8bcb2d0f47a574e115e9ab7e92beef7753d523f391a