Zobrazeno 1 - 10
of 147
pro vyhledávání: '"THOMAS J. DOWNAR"'
Autor:
NAM-IL TAK, MIN-HWAN KIM, HONG-SIK LIM, JAE MAN NOH, TIMOTHY J. DRZEWIECKI, VOLKAN SEKER, THOMAS J. DOWNAR, JOSEPH KELLY
Publikováno v:
Nuclear Engineering and Technology, Vol 45, Iss 6, Pp 745-752 (2013)
For thermo-fluid and safety analyses of a High Temperature Gas-cooled Reactor (HTGR), intensive efforts are in progress in the developments of the GAMMA+ code of Korea Atomic Energy Research Institute (KAERI) and the AGREE code of the University of M
Externí odkaz:
https://doaj.org/article/4b174d0b4a7f48249f738edd1bd220e7
Methods and Model Development for Coupled RELAP5/PARCS Analysis of the Atucha-II Nuclear Power Plant
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2011 (2011)
In order to analyze the steady state and transient behavior of CNA-II, several tasks were required. Methods and models were developed in several areas. HELIOS lattice models were developed and benchmarked against WIMS/MCNP5 results generated by NA-SA
Externí odkaz:
https://doaj.org/article/1a8ca7f4fac04a8d97a1663b381edfa3
Publikováno v:
Nuclear Science and Engineering. 197:291-307
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0eed315260958c769593f22a09a98d8c
https://doi.org/10.1080/00295639.2022.2082231
https://doi.org/10.1080/00295639.2022.2082231
Publikováno v:
Nuclear Science and Engineering. 195:741-765
The Transient Multilevel (TML) scheme in the MPACT code has reduced the computational burden for three-dimensional, full-core, time-dependent reactor simulations with pin-resolved detail. However, ...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1e77c34a6ea776da2225422d5f127e20
https://doi.org/10.1080/00295639.2020.1866388
https://doi.org/10.1080/00295639.2020.1866388
Publikováno v:
Journal of Computational and Theoretical Transport. 49:303-330
Two-dimensional/one-dimensional (2D/1D) methods have become popular for solving the 3D Boltzmann neutron transport equation on medium-to-large computing platforms. These methods can have a wide ran...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8b4afacfd1cfadaf9f37a8d428fc2625
https://doi.org/10.1080/23324309.2020.1819330
https://doi.org/10.1080/23324309.2020.1819330
Publikováno v:
Nuclear Science and Engineering. 195:50-68
Over the years, significant validation work for the neutronics code MPACT has been performed against zero-power critical benchmarks and measured data from operating nuclear power plants. Among all ...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6d8853520fb21fb8b165cc69566a43b4
https://doi.org/10.1080/00295639.2020.1780853
https://doi.org/10.1080/00295639.2020.1780853
Publikováno v:
Nuclear Technology. 206:839-861
The paper presents a self-adaptive feature selection algorithm we developed for solving high-dimensional uncertainty quantification problems. The development of the algorithm was motivated and supp...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::48eb50ce54c69511fed3c801dd0185d8
https://doi.org/10.1080/00295450.2020.1746620
https://doi.org/10.1080/00295450.2020.1746620
Publikováno v:
Nuclear Technology. 206:805-824
The Transient Reactor Test Facility (TREAT) was designed in the late 1950s to test nuclear fuels and materials under extreme conditions and has been recently restarted by the U.S. Department of Ene...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::63d9d2c5c9c14c5943c6d66c8c8a2ea7
https://doi.org/10.1080/00295450.2019.1703464
https://doi.org/10.1080/00295450.2019.1703464
Publikováno v:
Nuclear Technology. 206:825-838
The conventional two-step neutronics method used to perform full-core reactor neutronics simulation has been used successfully for light water reactor steady-state and transient analysis. The first...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f847f210ab161a92fe4cf1e3215e465f
https://doi.org/10.1080/00295450.2019.1672451
https://doi.org/10.1080/00295450.2019.1672451
Autor:
Jipu Wang, William R. Martin, Thomas J. Downar, Brendan Kochunas, Nathan C. Andrews, Lindsay Gilkey, Erik D. Walker, Benjamin S. Collins, Martin Pilch
Publikováno v:
Annals of Nuclear Energy. 178:109365
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9a26632ed5ce56756aaa20140992ce46
https://doi.org/10.1016/j.anucene.2022.109365
https://doi.org/10.1016/j.anucene.2022.109365