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Evans, Jordan A., Sweet, Ryan T., Medvedev, Pavel G., Wagner, Adrian R., Parisi, Carlo, Lange, Travis L., Perez, Emmanuel, Rice, Francine, Jue, Jan-Fong, Woolstenhulme, Eric, Keiser, Dennis D., Arafat, Yasir (2024) Uranium-zirconium hydride nuclear fuel performance in the NaK-cooled MARVEL microreactor. Journal of Nuclear Materials, 598. 155145 doi:10.1016/j.jnucmat.2024.155145

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Reference TypeJournal (article/letter/editorial)
TitleUranium-zirconium hydride nuclear fuel performance in the NaK-cooled MARVEL microreactor
JournalJournal of Nuclear Materials
AuthorsEvans, Jordan A.Author
Sweet, Ryan T.Author
Medvedev, Pavel G.Author
Wagner, Adrian R.Author
Parisi, CarloAuthor
Lange, Travis L.Author
Perez, EmmanuelAuthor
Rice, FrancineAuthor
Jue, Jan-FongAuthor
Woolstenhulme, EricAuthor
Keiser, Dennis D.Author
Arafat, YasirAuthor
Year2024 (September)Volume598
PublisherElsevier BV
DOIdoi:10.1016/j.jnucmat.2024.155145Search in ResearchGate
Generate Citation Formats
Mindat Ref. ID17387601Long-form Identifiermindat:1:5:17387601:7
GUID0
Full ReferenceEvans, Jordan A., Sweet, Ryan T., Medvedev, Pavel G., Wagner, Adrian R., Parisi, Carlo, Lange, Travis L., Perez, Emmanuel, Rice, Francine, Jue, Jan-Fong, Woolstenhulme, Eric, Keiser, Dennis D., Arafat, Yasir (2024) Uranium-zirconium hydride nuclear fuel performance in the NaK-cooled MARVEL microreactor. Journal of Nuclear Materials, 598. 155145 doi:10.1016/j.jnucmat.2024.155145
Plain TextEvans, Jordan A., Sweet, Ryan T., Medvedev, Pavel G., Wagner, Adrian R., Parisi, Carlo, Lange, Travis L., Perez, Emmanuel, Rice, Francine, Jue, Jan-Fong, Woolstenhulme, Eric, Keiser, Dennis D., Arafat, Yasir (2024) Uranium-zirconium hydride nuclear fuel performance in the NaK-cooled MARVEL microreactor. Journal of Nuclear Materials, 598. 155145 doi:10.1016/j.jnucmat.2024.155145
In(2024) Journal of Nuclear Materials Vol. 598. Elsevier BV

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Keiser, Dennis D., Robinson, Adam B., Jue, Jan-Fong, Medvedev, Pavel, Wachs, Daniel M., Finlay, M. Ross (2009) Microstructural development in irradiated U-7Mo/6061 Al alloy matrix dispersion fuel. Journal of Nuclear Materials, 393 (2). 311-320 doi:10.1016/j.jnucmat.2009.06.018
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