Zobrazeno 1 - 10
of 70
pro vyhledávání: '"Douglas E. Burkes"'
Publikováno v:
Heliyon, Vol 4, Iss 12, Pp e00920- (2018)
A simple, repeatable method for determination of the degree of grain refinement in irradiated Uranium-Molybdenum fuels has been developed. This method involves mechanical potting and polishing of samples along with examination using a scanning electr
Externí odkaz:
https://doaj.org/article/7509b2fe2050459d96e3147152904af2
Autor:
Todd S. Palmer, Nicholas H. Whitman, P. Alex Greaney, Douglas E. Burkes, David J. Senor, S. Aria Hosseini
Publikováno v:
Journal of Computational and Theoretical Transport. 50:483-506
We present a method for predicting thermal conductivity by deterministically solving the Boltzmann transport equation for gray phonons by utilizing arbitrary higher-order continuous finite elements...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0683e9bd147c29e1772d3a99ce08d623
https://doi.org/10.1080/23324309.2021.1900258
https://doi.org/10.1080/23324309.2021.1900258
Publikováno v:
Journal of Nuclear Materials. 524:164-176
Experiments show that irradiation-induced recrystallization speeds up the swelling kinetics in U-10 wt% Mo fuels. However, recrystallization mechanisms and the effect of initial grain microstructures on recrystallization kinetics are still unclear. I
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::719c7fca8a9ad65e63310718018ed4a4
https://doi.org/10.1016/j.jnucmat.2019.07.004
https://doi.org/10.1016/j.jnucmat.2019.07.004
Publikováno v:
Scientific Reports, Vol 9, Iss 1, Pp 1-10 (2019)
Scientific Reports
Scientific Reports
Spatially resolved analysis of uranium (U) isotopes in small volumes of actinide-bearing materials is critical for a variety of technical disciplines, including earth and planetary sciences, environmental monitoring, bioremediation, and the nuclear f
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::902e5331c64ea0182088bf568285d80e
http://link.springer.com/article/10.1038/s41598-019-48479-5
http://link.springer.com/article/10.1038/s41598-019-48479-5
Publikováno v:
Computational Materials Science. 161:107-118
A deep neural network was developed for the purpose of predicting thermal conductivity with a case study performed on neutron irradiated nuclear fuel. Traditional thermal conductivity modeling approaches rely on existing theoretical frameworks that d
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::8148f02a3ce75e0d4195cab70fc163e9
https://doi.org/10.1016/j.commatsci.2019.01.044
https://doi.org/10.1016/j.commatsci.2019.01.044
Publikováno v:
Frontiers in Materials, Vol 8 (2021)
Conventional rate theory often uses the mean field concept to describe the effect of inhomogeneous microstructures on the evolution of radiation induced defect and solute/fission product segregation. However, the spatial and temporal evolution of def
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::fa9d3f61d7b63cce9e3b2d6471b93db7
https://www.frontiersin.org/articles/10.3389/fmats.2021.682686/full
https://www.frontiersin.org/articles/10.3389/fmats.2021.682686/full
Advances in the nuclear fuel cycle and the introduction of novel fuel forms necessitate advances in fuel fabrication that encompass not only the development of commercially scalable fabrication techniques for novel fuel forms but also innovative synt
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1e955ec22053736c47dbe6f2af39f1d0
https://doi.org/10.1016/b978-0-08-102571-0.00011-2
https://doi.org/10.1016/b978-0-08-102571-0.00011-2
Publikováno v:
Open Engineering, Vol 8, Iss 1, Pp 243-260 (2018)
Monolithic UMo fuels have a higher uranium density than previously developed fuels. They have become the most promising fuels to be used in high-flux research and test reactors after the US Office of Material Management and Minimization Reactor Conve
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::bdb2c94de5ae5d4bcbaef231b504ea94
https://doaj.org/article/11bb4edf295347bda95fd3753b39a90d
https://doaj.org/article/11bb4edf295347bda95fd3753b39a90d
Autor:
Anthony Guzman, Douglas E. Burkes, Alan L. Schemer-Kohrn, David Willingham, Benjamin E. Naes, Jay G. Tarolli, Michael Dahl, Mark A. Rhodes
Publikováno v:
Journal of Nuclear Materials. 498:348-354
Uranium-molybdenum (U-Mo) monolithic fuels represent one option for converting civilian research and test reactors operating with high enriched uranium (HEU) to low enriched uranium (LEU), effectively reducing the threat of nuclear proliferation worl
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::12806e2f374bb2ce1f8adad7237eca91
https://doi.org/10.1016/j.jnucmat.2017.10.028
https://doi.org/10.1016/j.jnucmat.2017.10.028
Publikováno v:
Journal of Nuclear Materials. 494:182-191
A major goal of the Convert Program of the U.S. Department of Energy's National Nuclear Security Administration (DOE/NNSA) is to enable high-performance research reactors to operate with low-enriched uranium rather than the high-enriched uranium curr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f7bcf8af36e132481cc5c0ea8194b9c3
https://doi.org/10.1016/j.jnucmat.2017.07.006
https://doi.org/10.1016/j.jnucmat.2017.07.006