TY - GEN
T1 - Considerations for Thermal Annealing of Zr-Alloy Cladding During Dry Storage
AU - Cantonwine, Paul
AU - Karkkainen, Ryan
AU - Montgomery, Rose
AU - Cinbiz, M. Nedim
AU - Sasikumar, Yadu
AU - Torres, Ricardo
AU - Shimskey, Rick
AU - Petersen, Gordon
AU - Reed, Jeff
AU - Aumand, Matthieu
AU - Porter, Ian
AU - Mitchell, David
AU - Pan, Guirong
AU - Nair, Prasad
AU - Vitto, Steve
AU - Faldowski, Joe
N1 - Publisher Copyright:
© TopFuel 2025: Nuclear Reactor Fuel Performance.All rights reserved.
PY - 2025
Y1 - 2025
N2 - 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.
AB - 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.
KW - dry storage
KW - high burnup fuel
KW - LWR fuel
KW - thermal annealing
KW - transportation
KW - Zr cladding
UR - https://www.scopus.com/pages/publications/105030536784
U2 - 10.13182/TOPFUEL25-48078
DO - 10.13182/TOPFUEL25-48078
M3 - Conference contribution
AN - SCOPUS:105030536784
T3 - Proceedings of the TopFuel 2025: Nuclear Reactor Fuel Performance Conference
SP - 84
EP - 96
BT - Proceedings of the TopFuel 2025
PB - American Nuclear Society
T2 - TopFuel 2025: Nuclear Reactor Fuel Performance Conference
Y2 - 5 October 2025 through 9 October 2025
ER -