Zobrazeno 1 - 5
of 5
pro vyhledávání: '"Rian H. Prinsloo"'
Publikováno v:
Nuclear Science and Engineering. 197:308-332
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::eb451b12ec68488bf433ea5aff136ab7
https://doi.org/10.1080/00295639.2022.2108654
https://doi.org/10.1080/00295639.2022.2108654
Publikováno v:
Annals of Nuclear Energy. 87:659-670
The in-core fuel management optimisation (ICFMO) problem is the problem of finding an optimal fuel reload configuration for a nuclear reactor core. ICFMO may involve the pursuit of a single or multiple objectives, while satisfying several constraints
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0ac93b7c300d285c9d11c4e67851689d
https://doi.org/10.1016/j.anucene.2015.09.023
https://doi.org/10.1016/j.anucene.2015.09.023
Autor:
Maria Avramova, Adam Rosenkrantz, Danniëll Botes, Kostadin Ivanov, Khalid Elsakhawy, Rian H. Prinsloo
Publikováno v:
Annals of Nuclear Energy. 73:122-130
The purpose of this study was to develop a coupled accurate multi-physics model of the SAFARI-1 Material Testing Reactor (MTR), a facility that is used for both research and the production of medical isotopes. The model was developed as part of the S
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3a307ed79d212e3c502c4740d56992e6
https://doi.org/10.1016/j.anucene.2014.06.018
https://doi.org/10.1016/j.anucene.2014.06.018
Publikováno v:
Annals of Nuclear Energy. 68:70-88
Transverse-integrated nodal diffusion methods currently represent the standard in full core neutronic simulation. The primary shortcoming of this approach is the utilization of the quadratic transverse leakage approximation. This approach, although p
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0d5b7ad54f7878c9b2402abd3a0ec883
https://doi.org/10.1016/j.anucene.2014.01.010
https://doi.org/10.1016/j.anucene.2014.01.010
Publikováno v:
Journal of Engineering for Gas Turbines and Power. 132
The resurgence of High Temperature Reactor (HTR) technology has prompted the development and application of modern calculation methodologies, many of which are already utilized in the existing power reactor industry, to HTR designs. To this end, the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::12e81344c7fee231461b5fe02cb5a9a6
https://doi.org/10.1115/1.3095806
https://doi.org/10.1115/1.3095806