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Spent Fuel Storage and Transportation of Accident Tolerant Concepts: Cr-Coated Zirconium Alloy Cladding, FeCrAl Cladding, High Burnup and High Enrichment Fuel (NUREG/CR-7310)

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Publication Information

Manuscript Completed: October 2024
Date Published: June 2025

Prepared by:
W. Luscher
K. Geelhood
J. Brusky
C. Goodson

Pacific Northwest National Laboratory
Richland, Washington 99354

Lucas Kyriazidis, NRC Project Manager

Prepared for:
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

Availability Notice

Abstract

The U.S. Nuclear Regulatory Commission (NRC) is anticipating licensing applications and use of accident tolerant fuel (ATF) in U.S. commercial nuclear power reactors. Pacific Northwest National Laboratory is providing technical assistance to the NRC related to the newly proposed nuclear fuel and cladding designs.

This report focuses specifically on two ATF cladding concepts being investigated to replace the zirconium-based alloys currently used for fuel cladding and provides current state-of-the-industry information on material properties and fuel performance considerations relevant to the storage and transportation of spent nuclear fuel (SNF). For implementation of the near-term ATF concepts, fuel vendors and power reactor licensees are exploring the possibility of increasing the maximum enrichment of fuel up to 10% and the burnup limit to 75 or 80 GWd/MTU.

Currently, three U.S. nuclear fuel market suppliers are developing ATF designs: Global Nuclear Fuels (GNF) has tested several different iron-chromium-aluminum (FeCrAl) alloys, including Kanthal® APMT, C26M, and MA956 as well as Abrasion Resistant, More Oxidation Resistant (ARMOR) cladding, a coated zirconium alloy cladding with UO2 fuel; Westinghouse has tested Cr-coated ZIRLO® cladding and standard UO2 and chromium oxide-aluminum oxide (Cr2O3+Al2O3)-doped UO2 fuels; and Framatome has tested Cr-coated M5® cladding and Cr2O3-doped UO2 fuel.

To support the NRC’s readiness efforts, this report will identify and discuss degradation and failure modes of these ATF cladding concepts, including fuel performance characteristics that may not be addressed within existing regulatory documents. The implications of high burnup (> 62 GWd/MTU) and enhanced enrichment (> 5 w/o 235U) on the storage and transportation of SNF are also discussed. The recommendations made in this report are based on current publicly available data.

Page Last Reviewed/Updated Wednesday, June 25, 2025