Zobrazeno 1 - 10
of 44
pro vyhledávání: '"Gerhard Strydom"'
Autor:
Gerhard Strydom
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2013 (2013)
The Very High Temperature Reactor Methods Development group at the Idaho National Laboratory identified the need for a defensible and systematic uncertainty and sensitivity approach in 2009. This paper summarizes the results of an uncertainty and sen
Externí odkaz:
https://doaj.org/article/043f625b385d4c45ae05a0691c516c81
Publikováno v:
Annals of Nuclear Energy. 190:109896
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bb92ca5fd86d85107f4e7fdb36ae2397
https://doi.org/10.1016/j.anucene.2023.109896
https://doi.org/10.1016/j.anucene.2023.109896
Autor:
Tomooki Shiba, Kiyonobu Yamashita, Keiichiro Hori, Lap Cheng, Benjamin Cipiti, Michael Futterer, Hans Gougar, Gerhard Strydom, Christial Pohl, Abderfafi Ougouag, Hideyuki Sato
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1ea989aad205ca6ae4add3c204e82e6c
https://doi.org/10.2172/1869056
https://doi.org/10.2172/1869056
Autor:
Vincent Labouré, Javier Ortensi, Nicolas Martin, Paolo Balestra, Derek Gaston, Yinbin Miao, Gerhard Strydom
Publikováno v:
SSRN Electronic Journal.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::3ecdc2742588db2e175ecfb86bfd37e7
https://doi.org/10.2139/ssrn.4313600
https://doi.org/10.2139/ssrn.4313600
Autor:
Yutai Katoh, Nicholas R. Brown, Gerhard Strydom, Kurt A. Terrani, Takaaki Koyanagi, Cihang Lu
Publikováno v:
Nuclear Engineering and Design. 345:125-147
We conducted reactor performance calculations to assess the potential design basis accident performance of HTGR fuel designs. Three Fully Ceramic Microencapsulated (FCM) fueled HTGR designs were developed in a previous work (Lu et al., 2018). The max
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::98055a81187dfbf8638e175eb8c1b53f
https://doi.org/10.1016/j.nucengdes.2019.02.012
https://doi.org/10.1016/j.nucengdes.2019.02.012
Publikováno v:
Annals of Nuclear Energy. 165:108667
The International Atomic Energy Agency recently concluded a Coordinated Research Program (CRP) to evaluate the effect of propagation of uncertainties on design and safety parameters in High Temperature Gas-cooled Reactors (HTGRs). This CRP catalyzed
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9501513a4dfeb90881dd6aa2a6c08829
https://doi.org/10.1016/j.anucene.2021.108667
https://doi.org/10.1016/j.anucene.2021.108667
Publikováno v:
Nuclear Engineering and Design. 329:156-166
Uncertainty and sensitivity analysis is an indispensable element of any substantial attempt in reactor simulation validation. A Coordinated Research Program (CRP) supervised by the International Atomic Energy Agency was started to investigate the var
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::573235ddba552289187c21445bb2c3de
https://doi.org/10.1016/j.nucengdes.2017.12.008
https://doi.org/10.1016/j.nucengdes.2017.12.008