Zobrazeno 1 - 10
of 54
pro vyhledávání: '"Benjamin R. Betzler"'
Autor:
Brian J. Ade, Daniel P. Schappel, Benjamin R. Betzler, Grant W. Helmreich, Alberto Talamo, Dylan D. Richardson, Michael P. Trammel, Brian P. Jolly, Austin T. Schumacher, Kurt A. Terrani
Publikováno v:
Nuclear Science and Engineering. 196:1517-1538
Publikováno v:
Annals of Nuclear Energy. 190:109895
Publikováno v:
Nuclear Science and Engineering. 196:1539-1558
Autor:
Phillip C. Chesser, Florent Heidet, A. Bergeron, Briana Hiscox, Brian J Ade, Aaron J. Wysocki, Benjamin R. Betzler, Michael Scott Greenwood, Kurt A. Terrani, Nicholas R. Brown, James W. Sterbentz, Tommy V. Holschuh, Joseph R. Burns, Prashant K. Jain, J. D. Rader, Robert F. Kile, Jesse Heineman
Publikováno v:
Journal of Nuclear Engineering
Volume 2
Issue 1
Pages 8-85
Volume 2
Issue 1
Pages 8-85
Early cycle activities under the Transformational Challenge Reactor (TCR) program focused on analyzing and maturing four reactor core design concepts: two fast-spectrum systems and two thermal-spectrum systems. A rapid, iterative approach has been im
Publikováno v:
Nuclear Engineering and Design. 405:112193
Publikováno v:
Nuclear Science and Engineering. 194:1025-1043
Multigroup constants for deterministic methods that preserve the time-dependent physics of the neutron transport equations are derived. Alternative multigroup constant weighting spectra are discuss...
Autor:
Zack Taylor, Shane Henderson, Rui Hu, Robert Salko, Benjamin R. Betzler, Benjamin Collins, Markus H.A. Piro, Kaitlin Johnson, Jake W. McMurray, David Eugene Holcomb, Kyoung Lee, Aaron Graham
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b3abae84b49bbaa568e461b825122dc3
https://doi.org/10.2172/1827046
https://doi.org/10.2172/1827046
Publikováno v:
Annals of Nuclear Energy. 133:409-424
Molten salt reactor (MSR) concepts are being actively developed by several private companies, with some touting the fuel cycle benefits of this technology. Simulating the deployment of MSRs and their effect on fuel cycle transitions is the role of a
Publikováno v:
Annals of Nuclear Energy. 130:277-292
An iterative design process involving neutronic and thermal-hydraulic modeling and simulation has been employed to assess the feasibility of converting the Oak Ridge National Laboratory (ORNL) High Flux Isotope Reactor (HFIR) from high-enriched urani