Zobrazeno 1 - 10
of 60
pro vyhledávání: '"Travis W. Knight"'
Publikováno v:
Nuclear Science and Engineering. 195:1307-1326
A variety of normal operation and accident scenarios can generate thermal stresses large enough to cause cracking in ceramic fuel pellets. Cracking in fuel pellets can lead to reduced heat removal,...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7f55f93e83e5f155ee5652dd5f912156
https://doi.org/10.1080/00295639.2021.1932223
https://doi.org/10.1080/00295639.2021.1932223
Autor:
Denise Adorno Lopes, Travis W. Knight, Sobhan Patnaik, Theodore M. Besmann, Elwyn Roberts, Benjamin Spencer
Publikováno v:
Nuclear Engineering and Design. 384:111482
A variety of normal operation and accident scenarios can generate thermal stresses large enough to cause cracking in light-water reactor (LWR) fuel pellets. Cracking of fuel pellets can lead to reduced heat removal, larger centerline temperatures, an
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e6d116f19d14d7825945e509a72ce2b9
https://doi.org/10.1016/j.nucengdes.2021.111482
https://doi.org/10.1016/j.nucengdes.2021.111482
Publikováno v:
Journal of Nuclear Materials. 556:153163
Standard UO2 fuel pellets used in light-water reactors fracture during irradiation due to the large thermal gradient in the radial direction. Over the decades, numerous researchers have explored fuel cracking from experimental and modeling points of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9519b14e9d486d960a237729ff42dcf0
https://doi.org/10.1016/j.jnucmat.2021.153163
https://doi.org/10.1016/j.jnucmat.2021.153163
Publikováno v:
Journal of Nuclear Materials. 553:153004
While it is well known that ceramic UO 2 fuel cracks early in its life in a nuclear reactor, it is very difficult to collect in-reactor data regarding fuel cracking initiation and propagation to validate fracture models in fuel performance codes. Mos
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e9651405e52007660a504f1af97b0283
https://doi.org/10.1016/j.jnucmat.2021.153004
https://doi.org/10.1016/j.jnucmat.2021.153004
Publikováno v:
Progress in Nuclear Energy. 99:147-154
Purpose U3Si2 is under investigation as an accident tolerant fuel due to its advantageous thermo-physical properties, including; high uranium density, high thermal conductivity, and high melting temperature. However, mechanical data available for the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::dc44be5f33ced6c7fabfd1fc153e7c9e
https://doi.org/10.1016/j.pnucene.2017.05.007
https://doi.org/10.1016/j.pnucene.2017.05.007
Publikováno v:
Transactions of the American Nuclear Society - Volume 121.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::54fc032ee3b425f386c031fae6cf7641
https://doi.org/10.13182/t31122
https://doi.org/10.13182/t31122
Publikováno v:
Transactions of the American Nuclear Society - Volume 121.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d8ddc811acd3503a9abbf7d5c2061677
https://doi.org/10.13182/t31316
https://doi.org/10.13182/t31316