Design Features for Enhancing InternationalSafeguards of Away-from-Reactor Dry Storage for Spent LWR Fuel (NUREG/CR-4517, PNL-5321)

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Publication Information

Manuscript Completed: February 1986
Date Published: October 1986

Prepared by:
F.P. Roberts, N.L. Harms
P.O. Box 999
Pacific Northwest Laboratory
Richland, Washington 99352
Operated by Battelle Memorial Institute

Prepared for:
Division of Safeguards
Office of Nuclear Material Safety and Safeguards
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

NRC FIN B-2475

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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.