Zobrazeno 1 - 10
of 55
pro vyhledávání: '"David J Diamond"'
Publikováno v:
Nuclear Technology. 206:322-338
We discuss liquid-fuel molten salt (cooled) reactors (MSRs); how they will operate under normal, transient, and accident conditions; and the results of an expert elicitation to determine the corres...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::260eacf60bf8ec469b3fd24f24477e19
https://doi.org/10.1080/00295450.2019.1590077
https://doi.org/10.1080/00295450.2019.1590077
Autor:
Sheng Zhang, David J. Diamond, Hsun-Chia Lin, Qiuping Lv, Shanbin Shi, Stephen M. Bajorek, Xiaodong Sun, Richard M. Christensen, Graydon L. Yoder, Yujun Guo
Publikováno v:
Annals of Nuclear Energy. 124:257-269
The Advanced High Temperature Reactor (AHTR) is a conceptual design of a Fluoride salt-cooled High-temperature Reactor (FHR) utilizing 7LiF-BeF2 (66–34 mol%) as its primary coolant. To identify key phenomena that impose potential challenges on ther
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1ce2ce9591ee6a67945e001996f8e9cc
https://doi.org/10.1016/j.anucene.2018.08.038
https://doi.org/10.1016/j.anucene.2018.08.038
Publikováno v:
Annals of Nuclear Energy. 123:172-179
On the path to deployment of any reactor, modeling tool verification and validation is a key step. Fluoride-Salt-Cooled High Temperature Reactors (FHR) pose challenges to neutronics modeling and simulation tools due to several design features of the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9d3d451bde1517a4858cc485a17be49a
https://doi.org/10.1016/j.anucene.2018.08.035
https://doi.org/10.1016/j.anucene.2018.08.035
Autor:
Bojan Petrovic, Stephen M. Bajorek, Xiaodong Sun, Paul Burke, Dingkang Zhang, Graydon L. Yoder, Yujun Guo, Farzad Rahnema, David J. Diamond
Publikováno v:
Annals of Nuclear Energy. 121:540-551
This study identifies the phenomena that impact the accuracy of the multiphysics analysis of fluoride salt-cooled high temperature reactors (FHR) and categorizes the level of coupling needed to model these phenomena with sufficient accuracy in the co
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f563c688e6ea454ceb74fe59cfad5230
https://doi.org/10.1016/j.anucene.2018.07.039
https://doi.org/10.1016/j.anucene.2018.07.039
Publikováno v:
Nuclear Technology. 196:238-247
A TRACE/PARCS model has been developed to analyze anticipated transient without SCRAM (ATWS) events for a boiling water reactor (BWR) operating in the maximum extended load line limit analysis-plus (MELLLA+) expanded operating domain. The MELLLA+ dom
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0d5c7656a67d51a7f3349e77eeab3125
https://doi.org/10.13182/nt16-29
https://doi.org/10.13182/nt16-29