Behavior of metallic fast reactor fuels during an overpower transient

Wachs, Daniel M.; Capriotti, Luca; Porter, Douglas

doi:10.1016/j.jnucmat.2021.153304

Title: Behavior of metallic fast reactor fuels during an overpower transient

Journal Article · 01 December 2021 · Journal of Nuclear Materials

DOI: https://doi.org/10.1016/j.jnucmat.2021.153304 · OSTI ID:1822573

Wachs, Daniel M.; Capriotti, Luca; Porter, Douglas

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Sponsoring Organization:: USDOE

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 1822573

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 557 Journal Issue: C; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: Netherlands

Language:: English

References (12)

Metallic fast reactor fuels Hofman, G. L.; Walters, L. C.; Bauer, T. H. Progress in Nuclear Energy, Vol. 31, Issue 1-2 https://doi.org/10.1016/0149-1970(96)00005-4	journal	January 1997
Transient Testing of Nuclear Fuels and Materials in the United States Wachs, Daniel M. JOM, Vol. 64, Issue 12 https://doi.org/10.1007/s11837-012-0482-2	journal	October 2012
Behavior of mixed-oxide fuel elements during an overpower transient Tsai, H.; Neimark, L. A.; Asaga, T. Journal of Nuclear Materials, Vol. 204 https://doi.org/10.1016/0022-3115(93)90220-S	journal	September 1993
Constituent redistribution in U–Pu–Zr fuel during irradiation Kim, Yeon Soo; Hofman, G. L.; Hayes, S. L. Journal of Nuclear Materials, Vol. 327, Issue 1 https://doi.org/10.1016/j.jnucmat.2004.01.012	journal	April 2004
Irradiation behavior of metallic fast reactor fuels Pahl, R. G.; Porter, D. L.; Crawford, D. C. Journal of Nuclear Materials, Vol. 188 https://doi.org/10.1016/0022-3115(92)90447-S	journal	June 1992
Neutron Radiography of Irradiated Nuclear Fuel at Idaho National Laboratory Craft, Aaron E.; Wachs, Daniel M.; Okuniewski, Maria A. Physics Procedia, Vol. 69 https://doi.org/10.1016/j.phpro.2015.07.068	journal	January 2015
Fuel-cladding interaction layers in irradiated U-ZR and U-PU-ZR fuel elements. Keiser, D. D. https://doi.org/10.2172/885496	report	January 2006
An analysis of nuclear fuel burnup in the AGR-1 TRISO fuel experiment using gamma spectrometry, mass spectrometry, and computational simulation techniques Harp, Jason M.; Demkowicz, Paul A.; Winston, Philip L. Nuclear Engineering and Design, Vol. 278 https://doi.org/10.1016/j.nucengdes.2014.07.041	journal	October 2014
Behavior of Modern Metallic Fuel in TREAT Transient Overpower Tests Bauer, Theodore H.; Wright, Arthur E.; Robinson, William R. Nuclear Technology, Vol. 92, Issue 3 https://doi.org/10.13182/NT92-325	journal	December 1990
A US perspective on fast reactor fuel fabrication technology and experience part I: metal fuels and assembly design Burkes, Douglas E.; Fielding, Randall S.; Porter, Douglas L. Journal of Nuclear Materials, Vol. 389, Issue 3 https://doi.org/10.1016/j.jnucmat.2009.02.035	journal	June 2009
Metal Fuel Ogata, T. Comprehensive Nuclear Materials https://doi.org/10.1016/B978-0-08-056033-5.00049-5	book	January 2012
Temperature gradient driven constituent redistribution in UZr alloys Hofman, G. L.; Hayes, S. L.; Petri, M. C. Journal of Nuclear Materials, Vol. 227, Issue 3 https://doi.org/10.1016/0022-3115(95)00129-8	journal	January 1996

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