Zobrazeno 1 - 6
of 6
pro vyhledávání: '"Danniëll Botes"'
Publikováno v:
Nuclear Technology and Radiation Protection, Vol 36, Iss 2, Pp 107-115 (2021)
This work addresses the problem of propagating uncertainty from group-wise neutron cross-sections to the results of neutronics diffusion calculations. Automatic differentiation based on dual number arithmetic was applied to uncertainty propagation in
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::59c36a2fb2be398a83496a0b586fe029
https://doi.org/10.2298/ntrp2102107b
https://doi.org/10.2298/ntrp2102107b
Publikováno v:
Annals of Nuclear Energy. 99:444-454
Nodal diffusion methods are often used for full core neutronic analysis. They require few-group homogenised neutron cross sections for every heterogeneous sub-region of the core. The homogenised cross sections are pre-calculated at various reactor st
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::557d580a0174c4099b31f1480f82551a
https://doi.org/10.1016/j.anucene.2016.09.051
https://doi.org/10.1016/j.anucene.2016.09.051
Publikováno v:
Annals of Nuclear Energy. 151:107925
Automatic differentiation (AD) is a set of techniques which allows the numeric evaluation of derivatives of functions calculated by a computer program. In recent years, interest in AD has grown significantly in many disciplines, especially in the con
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1bb45b17c1fafe2bfe34641d31acca6c
https://doi.org/10.1016/j.anucene.2020.107925
https://doi.org/10.1016/j.anucene.2020.107925
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
Autor:
Pavel M. Bokov, Danniëll Botes
Publikováno v:
Annals of Nuclear Energy. 64:156-168
Few group, homogenized neutron cross sections are represented as a function of various state parameters through multidimensional Lagrange interpolation. The interpolation is built on a Clenshaw-Curtis sparse grid by applying the method of mean weight
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::25dbdfcf6c0835e1f978705453ea9f53
https://doi.org/10.1016/j.anucene.2013.09.033
https://doi.org/10.1016/j.anucene.2013.09.033
