Zobrazeno 1 - 10
of 52
pro vyhledávání: '"Kevin T. Clarno"'
Autor:
Kevin T. Clarno, Praneel P. Gulabrao
Publikováno v:
Nuclear Science and Engineering. 195:161-172
Photon buildup is a function of energy, medium, and geometry and therefore must be specifically calculated for the case of interest. The Martian atmosphere, mostly comprising carbon dioxide, is bec...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c54641578db1dbc9291191257ca3d6ef
https://doi.org/10.1080/00295639.2020.1794455
https://doi.org/10.1080/00295639.2020.1794455
Publikováno v:
Annals of Nuclear Energy. 133:46-58
The MPACT neutronics module of the Consortium for Advanced Simulation of Light Water Reactors (CASL) core simulator is a 3D whole core transport code being developed for the CASL toolset known as the Virtual Environment for Reactor Analysis (VERA). K
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8bc61954816e3f6787db2d60c45149ed
https://doi.org/10.1016/j.anucene.2019.05.010
https://doi.org/10.1016/j.anucene.2019.05.010
Autor:
Marc-Oliver Delchini, Robert Salko, W. D. Pointer, Stuart R. Salttery, Annalisa Manera, William Gurecky, Kevin T. Clarno, Victor Petrov
Publikováno v:
Nuclear Technology. 205:1697-1706
The Consortium for Advanced Simulation of Light Water Reactors is developing a core simulator capability known as the Virtual Environment for Reactor Applications (VERA) to address nuclear ...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::813f387179b03d6053bba84e50f9c4ce
https://doi.org/10.1080/00295450.2019.1585734
https://doi.org/10.1080/00295450.2019.1585734
Publikováno v:
Nuclear Engineering and Design. 341:248-258
A new fuel modeling capability, CTFFuel, is developed from the subchannel code, CTF. This code is a standalone interface to the CTF fuel rod models, allowing for fuel rod simulations to be run independently from the fluid. This paper provides an over
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9126b8946153c914833d3df02bf2b20b
https://doi.org/10.1016/j.nucengdes.2018.11.010
https://doi.org/10.1016/j.nucengdes.2018.11.010
Publikováno v:
Annals of Nuclear Energy. 168:108893
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::56e879137fabc706a100383a5d6052ab
https://doi.org/10.1016/j.anucene.2021.108893
https://doi.org/10.1016/j.anucene.2021.108893
Publikováno v:
Nuclear Engineering and Design. 333:131-144
This article demonstrates the application of the Virtual Environment for Reactor Applications simulation environment to screen for pellet-clad interaction amongst the core-wide fuel rods within a pressurized water reactor, with emphasis on the multi-
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::76e9df0005284cac86357e1e11a91846
https://doi.org/10.1016/j.nucengdes.2018.04.018
https://doi.org/10.1016/j.nucengdes.2018.04.018
Autor:
Jeffrey J. Powers, Richard L. Williamson, Roger P. Pawlowski, R. J. Gardner, Kevin T. Clarno, Kyle A. Gamble, Stephen Novascone, Shane Stimpson
Publikováno v:
Nuclear Engineering and Design. 327:172-186
The Consortium for Advanced Simulation of Light Water Reactors (CASL) aims to provide high-fidelity multiphysics simulations of light water nuclear reactors. To accomplish this, CASL is developing the Virtual Environment for Reactor Applications (VER
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::42dadd41b634921d29189005604eadc0
https://doi.org/10.1016/j.nucengdes.2017.12.015
https://doi.org/10.1016/j.nucengdes.2017.12.015
Publikováno v:
Journal of Nuclear Materials. 554:153089
A new formulation for redistribution of constituents in metallic U-Pu-Zr nuclear fuel is presented that can incorporate the contributions from fission products. The formulation is based on the thermodynamic driving forces derived from the generalized
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fc2397c4b7bef4c013474028cbf49294
https://doi.org/10.1016/j.jnucmat.2021.153089
https://doi.org/10.1016/j.jnucmat.2021.153089
Publikováno v:
Nuclear Engineering and Technology, Vol 49, Iss 6, Pp 1240-1249 (2017)
An essential component of the neutron transport solver is the resonance self-shielding calculation used to determine equivalence cross sections. The neutron transport code, MPACT, is currently using the subgroup self-shielding method, in which the me
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::7dba4d5d2f978eaf50ae85b7827a6518
https://doi.org/10.1016/j.net.2017.07.006
https://doi.org/10.1016/j.net.2017.07.006
Autor:
Benjamin Collins, Thomas J. Downar, Andrew T. Godfrey, Brendan Kochunas, Yuxuan Liu, William A. Wieselquist, Jess C. Gehin, Daniel Jabaay, Shane Stimpson, Robert Salko, Aaron Graham, Kevin T. Clarno, Kang Seog Kim, Scott Palmtag
Publikováno v:
Nuclear Science and Engineering. 185:217-231
This paper describes the methodology developed and implemented in the Virtual Environment for Reactor Applications Core Simulator (VERA-CS) to perform high-fidelity, pressurized water reactor (PWR), multicycle, core physics calculations. Depletion of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::173dc1fe926efef52afaba9fa0c87274
https://doi.org/10.13182/nse16-39
https://doi.org/10.13182/nse16-39