Transient testing of uranium silicide fuel in zircaloy and silicon carbide cladding

Kamerman, David; Woolstenhulme, Nicolas; Imholte, Devin; Fleming, Austin; Jensen, Colby; Folsom, Charles; Woolum, Connor; Tritthart, Korbin; Schulthess, Jason; Wachs, Dan

doi:10.1016/j.anucene.2021.108410

Transient testing of uranium silicide fuel in zircaloy and silicon carbide cladding

Journal Article · Mon May 24 00:00:00 EDT 2021 · Annals of Nuclear Energy

DOI:https://doi.org/10.1016/j.anucene.2021.108410· OSTI ID:2203089

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Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Using the newly restarted Transient Reactor Test (TREAT) facility at Idaho National Laboratories, fresh (unirradiated) U₃Si₂ fuel pellets were tested under reactivity-initiated accident conditions in dry helium capsules. These tests were performed with total energy depositions sufficient to induce melting of the U₃Si₂ fuel pellets based on available thermophysical property data. The instrumented experiments utilized in-pile thermocouples and infrared pyrometers to measure the cladding temperature during the transient, which are in reasonable agreement with predicted peak cladding temperatures using a simple BISON fuel performance model. This same model is then used to predict expected cladding stresses during the transients in areas where pellet cladding interaction is expected. It was shown that for transient energy depositions up to 528J/g rod like geometry of the test articles was maintained. While it is acknowledged that more confirmatory testing is required in more prototypic environments, these first of their kind experiments have demonstrated that unirradiated U₃Si₂ fuel and unirradiated SiC-SiC claddings can likely retain a “rod like” geometry for transient energy depositions up to 528J/g.

View Accepted Manuscript (DOE)

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE; USDOE Office of Nuclear Energy (NE), Nuclear Fuel Cycle and Supply Chain. Office of Advanced Fuels Technologies

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 2203089

Alternate ID(s):: OSTI ID: 1784420

Report Number(s):: INL/JOU--20-59957-Rev000

Journal Information:: Annals of Nuclear Energy, Journal Name: Annals of Nuclear Energy Vol. 160; ISSN 0306-4549

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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