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Design Features for Enhancing International Safeguards of Away-from- Reactor Dry Storage for Spent LWR Fuel (NUREG/CR-4517)

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Publication Information
Abstract

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NUREG/CR-4517 (PDF - 1.31 MB)

Publication Information

Manuscript Completed: February 1986
Date Published: October 1986

Prepared by
F. P. Roberts, N. L. Harms

Pacific Northwest Laboratory
Richland, WA 99352

Prepared for
Division of Safeguards
Office of Nuclear Material Safety and Safeguards
U.S. Nuclear Regulatory Commission
Washington., D.C. 205655
NRC FIN B2475

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Abstract

The Pacific Northwest Laboratory has performed a study for the Nuclear Regulatory Commission to identify and analyze design features that can facilitate the implementation of IAEA safeguards at away-from-reactor facilities for dry storage of light water reactor spent fuels. Thirteen specific design features are identified that can enhance verification of nuclear material flow and inventory. These are assessed from the viewpoint of safeguards effectiveness and possible impacts on the IAEA and the operator of the AFR facility.