Sister Rod Destructive Examinations (FY22)

Montgomery, Rose; Bevard, Bruce Balkcom

doi:10.2172/1976043

2023

DOI: 10.2172/1976043

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Sister Rod Destructive Examinations (FY22)

Rose Montgomery¹,

Bruce Balkcom Bevard²

Abstract: This report documents work performed under the Spent Fuel and Waste Disposition's Spent Fuel and Waste Science and Technology program for the US Department of Energy (DOE) Office of Nuclear Energy (NE).

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2024

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Cited by 2 publications

References 7 publications

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Metallographic examinations and hydrogen measurements of high-burnup spent nuclear fuel cladding

Ayanoglu,

Montgomery,

Harp

et al. 2024

Journal of Nuclear Materials

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Metallographic examinations and hydrogen measurements of high-burnup spent nuclear fuel cladding

Ayanoglu,

Montgomery,

Harp

et al. 2024

Journal of Nuclear Materials

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Key results from examinations of seven high burnup pressurized water reactor spent nuclear fuel rods

Montgomery,

Bevard,

Cantonwine

et al. 2024

Front. Nucl. Eng.

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At present, spent nuclear fuel (SNF) assemblies discharged from US commercial power plants are placed into dry storage following a short cooling time (<10 years) in the plant’s spent fuel pool. The process of packaging the spent fuel into dry-storage canisters includes a drying step to remove residual water from the canister. During the drying process, the fuel rod cladding may reach temperatures as high as 400°C. Oak Ridge National Laboratory (ORNL) is performing destructive examinations of high burnup (HBU) (>45 GWd/MTU) SNF rods to address knowledge and data gaps related to extended interim storage and eventual transportation for disposal. The rods examined include four different kinds of fuel rod cladding: standard Zircaloy-4 (Zirc-4), low-tin (LT) Zirc-4, ZIRLO, and M5. Three rods were subjected to a thermal transient to assess the effects of decay-heat-driven high temperatures expected during vacuum drying of the fuel as it is prepared for interim dry storage. The examinations focus on the composite fuel rod performance, as compared with the performance of defueled rod cladding, and establish the baseline mechanical properties of a fuel rod before interim dry storage. The key results of these examinations are presented, including the measured mechanical and fatigue properties, observations of cladding hydrogen pickup and hydride reorientation effects on rod performance, effects of the simulated drying temperatures on rod performance, and general conclusions of SNF performance in extended interim dry storage and transport. The rods were found to be strong and durable in the expected loading conditions, even considering the formation of radial hydrides associated with vacuum drying. The combined testing provides a broad body of data supporting extended interim storage and transportation performance of HBU spent fuel.

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Sister Rod Destructive Examinations (FY22)

Abstract: This report documents work performed under the Spent Fuel and Waste Disposition's Spent Fuel and Waste Science and Technology program for the US Department of Energy (DOE) Office of Nuclear Energy (NE).

Cited by 2 publications

References 7 publications

Metallographic examinations and hydrogen measurements of high-burnup spent nuclear fuel cladding

Metallographic examinations and hydrogen measurements of high-burnup spent nuclear fuel cladding

Key results from examinations of seven high burnup pressurized water reactor spent nuclear fuel rods

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