Considerations for Thermal Annealing of Zr-Alloy Cladding During Dry Storage

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

In January 2025, the U.S. Department of Energy (DOE) sponsored a technical workshop with fuel vendors that provided a forum for increased collaboration on backend fuel cycle research. The workshop reviewed observations of thermal annealing of irradiated zirconium alloys in simulated dry storage conditions and discussed implications to the industry's interest in reducing wet storage to optimize operational flexibility and the expected trend of increasing discharge burnup (and decay heats), which could lead to an increase in dry storage temperatures. One approach to accommodate increased decay heats in dry storage is to increase the regulatory temperature limit during dry storage, which is now 400°C. However, this could lead to thermal annealing of the cladding, which will tend to increase creep rates, creep strains, and ductility while decreasing yield strength. These considerations are compounded by bonding between the pellet and cladding at high burnup, which results in the pellet carrying more load during fuel rod deformations, especially in bending, which is the dominant deformation phenomenon in canister drop analyses. Because the U.S. Nuclear Regulatory Commission (NRC) recommends yield strength as a primary failure criterion for accident analyses in storage and transportation, particularly for canister drop scenarios, the purpose of the workshop was to develop options for alternative failure criterion that could replace yield strength in canister drop analyses. Topics discussed were (1) the regulatory framework, (2) the effect of thermal annealing on microhardness and tensile properties of cladding materials, (3) the effect of thermal annealing on fuel rod failure during bending, bending fatigue, and pinch loading, and (4) an alternative failure criterion for canister drop analyses. This paper provides a summary of the key discussions and outcomes of the workshop.

Original languageEnglish
Title of host publicationProceedings of the TopFuel 2025
Subtitle of host publicationNuclear Reactor Fuel Performance Conference
PublisherAmerican Nuclear Society
Pages84-96
Number of pages13
ISBN (Electronic)9780894482281
DOIs
StatePublished - 2025
EventTopFuel 2025: Nuclear Reactor Fuel Performance Conference - Nashville, United States
Duration: Oct 5 2025Oct 9 2025

Publication series

NameProceedings of the TopFuel 2025: Nuclear Reactor Fuel Performance Conference

Conference

ConferenceTopFuel 2025: Nuclear Reactor Fuel Performance Conference
Country/TerritoryUnited States
CityNashville
Period10/5/2510/9/25

Keywords

  • dry storage
  • high burnup fuel
  • LWR fuel
  • thermal annealing
  • transportation
  • Zr cladding

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