The Industry Spent Fuel Storage Handbook (“the Handbook”) addresses the relevant aspects of at-reactor spent (or used) nuclear fuel (SNF) storage in the United States. With the prospect of SNF being stored at reactor sites for the foreseeable future, it is expected that all U.S. nuclear power plants will have to implement at-reactor dry storage by 2025 or shortly thereafter. The Handbook provides a broad overview of recent developments for storing SNF at U.S. reactor sites, focusing primarily on at-reactor dry storage of SNF.

The effective termination of the Yucca Mountain program by the U.S. Administration in 2009 has further delayed the construction and operation of a permanent disposal facility for used fuel and high level radioactive waste (HLW) in the United States. In concert with this decision, the President directed the Energy Secretary to establish the Blue Ribbon Commission on America's Nuclear Future to review and provide recommendations on options for managing used fuel and HLW.

This report presents the results of a critical review of the technological challenges to the growth of nuclear energy, emerging advanced technologies that would have to be deployed, and fuel cycle strategies that could conceivably involve interim storage, plutonium recycling in thermal and fast reactors, reprocessed uranium recycling, and transmutation of minor actinide elements and fission products before eventual disposal of residual wastes.

The U.S. industry’s limited efforts at licensing transportation packages characterized as “highcapacity,”
or containing “high-burnup” (>45 GWd/MTU) commercial spent nuclear fuel
(CSNF), or both, have not been successful considering existing spent-fuel inventories that will
have to be eventually transported. A holistic framework is proposed for resolving several CSNF
transportation issues. The framework considers transportation risks, spent-fuel and cask-design

This report summarizes the results of EPRI’s multi-year research effort to assess cladding
performance under normal and hypothetical accident conditions of spent nuclear fuel
transportation.

The purpose of this interim staff guidance (ISG) is to supplement standard review plan guidance
for evaluating the helium leakage testing and ASME Code1
required pressure
(hydrostatic/pneumatic) testing that is specified for the dry storage system (DSS) confinement
boundary. These acceptance tests are necessary to clearly demonstrate that the DSS
confinement boundary has been fabricated in accordance with the design criteria, and that its
operation complies with the intended safety bases of the confinement system and regulatory

Under the current guidance in ISG-1, Revision 1, “Damaged Fuel,” the definition of intact fuel
includes fuel rods containing no cladding defects greater than pinhole leaks or hairline cracks.
During the cask water removal process parts of, or all of, the fuel rods will be exposed to a
gaseous atmosphere. If the gaseous atmosphere is oxidizing, oxidation of fuel pellets or fuel
fragments can occur if a cladding breach exists (such as a pinhole). Oxidation may occur

Given the growing industry need to store spent reactor fuel of increasingly higher burnups and
heat loads in dry storage casks, and eventually to transport that same spent fuel in
transportation packages, analyzing the performance of casks and other radioactive material
packages has become a greater challenge. Finite Element, Finite Difference, and Finite
Volume analysis computer codes, defined here as Computational Modeling Software (CMS),
are tools used by many licensees to analyze cask and package performance in the structural

The standard review plans for storage of spent nuclear fuel and transportation of fissile
materials do not address, in detail, the technical considerations for crediting the neutron
absorber content of metal matrix composites used for preventing nuclear criticality. The Division
of Spent Fuel Storage and Transportation (SFST) considers the application of acceptance
criteria and methodology described in the recently developed American Standard for Testing
and Materials (ASTM) standard practice C1671-07, “Standard Practice for Qualification and