Engineering Assessment of UO2 and Cladding Behavior under High Burnup LOCA Conditions

Nathan Capps; Ryan Sweet; Jason Harp; Christian Petrie

doi:10.2172/1822042

Engineering Assessment of UO₂ and Cladding Behavior under High Burnup LOCA Conditions

Nathan Capps, Ryan Sweet, Jason Harp, Christian Petrie

Research output: Book/Report › Commissioned report

Abstract

To maximize the data extracted from a limited number of high-burnup fuel rod samples, several modeling efforts were performed to elucidate the fuel and the cladding responses of these fuels under transient conditions. These objectives were (1) to determine the role of the fuel stress state in fuel pulverization, (2) to ascertain the differences between conditions of cladding burst during experiments and those expected during a commercial reactor transient, and (3) to develop a method to conservatively calculate the geometry of the cladding rupture’s opening to inform fuel dispersal susceptibility.

Original language	English
Place of Publication	United States
DOIs	https://doi.org/10.2172/1822042
State	Published - 2021

Keywords

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS

Access to Document

10.2172/1822042

Cite this

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title = "Engineering Assessment of UO2 and Cladding Behavior under High Burnup LOCA Conditions",

abstract = "To maximize the data extracted from a limited number of high-burnup fuel rod samples, several modeling efforts were performed to elucidate the fuel and the cladding responses of these fuels under transient conditions. These objectives were (1) to determine the role of the fuel stress state in fuel pulverization, (2) to ascertain the differences between conditions of cladding burst during experiments and those expected during a commercial reactor transient, and (3) to develop a method to conservatively calculate the geometry of the cladding rupture{\textquoteright}s opening to inform fuel dispersal susceptibility.",

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AU - Harp, Jason

AU - Petrie, Christian

PY - 2021

Y1 - 2021

N2 - To maximize the data extracted from a limited number of high-burnup fuel rod samples, several modeling efforts were performed to elucidate the fuel and the cladding responses of these fuels under transient conditions. These objectives were (1) to determine the role of the fuel stress state in fuel pulverization, (2) to ascertain the differences between conditions of cladding burst during experiments and those expected during a commercial reactor transient, and (3) to develop a method to conservatively calculate the geometry of the cladding rupture’s opening to inform fuel dispersal susceptibility.

AB - To maximize the data extracted from a limited number of high-burnup fuel rod samples, several modeling efforts were performed to elucidate the fuel and the cladding responses of these fuels under transient conditions. These objectives were (1) to determine the role of the fuel stress state in fuel pulverization, (2) to ascertain the differences between conditions of cladding burst during experiments and those expected during a commercial reactor transient, and (3) to develop a method to conservatively calculate the geometry of the cladding rupture’s opening to inform fuel dispersal susceptibility.

KW - 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS

U2 - 10.2172/1822042

DO - 10.2172/1822042

M3 - Commissioned report

BT - Engineering Assessment of UO2 and Cladding Behavior under High Burnup LOCA Conditions

CY - United States