Zobrazeno 1 - 10
of 33
pro vyhledávání: '"Fu, Yuanguang"'
Publikováno v:
In Annals of Nuclear Energy 1 September 2024 204
Publikováno v:
Yuanzineng kexue jishu, Vol 57, Iss 6, Pp 1131-1139 (2023)
Numerical reactor is aimed to show the physical phenomena by means of high-fidelity numerical simulations. Monte Carlo method is commonly used in numerical reactor. JMCT (joint Monte Carlo transport) is a large-scale, high-fidelity, three-dimensional
Externí odkaz:
https://doaj.org/article/a748edc8909348ca86c6409fe3be8983
Autor:
Wang, Xin, Yu, Yi, Li, Xunzhao, Feng, Jingchao, Zhang, Baoyin, Yan, Congchong, Fu, Yuanguang, Xu, Jingjie
Publikováno v:
In Annals of Nuclear Energy 15 September 2023 190
Publikováno v:
EPJ Web of Conferences, Vol 302, p 09001 (2024)
Global tallying problem is hard to be solved efficiently when using Monte carlo method to simulate neutron transport equation, especially for sys- tem with big scale and/or strong imbalanced characteristics. Among numerous global variance reduction m
Externí odkaz:
https://doaj.org/article/94c4d78a91394b40bcfe9a22b2de4c1f
Publikováno v:
In Annals of Nuclear Energy October 2022 176
Publikováno v:
Yuanzineng kexue jishu, Vol 56, Iss 2, Pp 316-325 (2022)
During the source iteration process of Monte Carlo criticality calculation with particle parallel, there exists stochastic fluctuate which may cause unbalanced allocation of number of fission banks. Without inducing bank adjustment algorithm, a fewer
Externí odkaz:
https://doaj.org/article/07a3fddd115243b0b6b8cc7aceb37f6d
Publikováno v:
Yuanzineng kexue jishu, Vol 56, Iss 11 (2022)
The fuel assembly and fuel rod bundle of sodium-cooled fast reactor are arranged in a triangle form. The fuel assembly adopts closed structure deign without mixing of coolant between assemblies, which is cooled by the sodium coolant through the distr
Externí odkaz:
https://doaj.org/article/d3688d5783e1487b91959fc6059071ac
Autor:
Cai, Li, Liu, Peng, Wu, Xiong, Li, Rui, Zeng, Xian, Fu, Yuanguang, Zhang, Xiangju, Shi, Dunfu, Li, Dongsheng, Deng, Li
Publikováno v:
In Annals of Nuclear Energy March 2021 152
Autor:
Li Deng, Li Cai, Rui Li, Xiangju Zhang, Xiong Wu, Xian Zeng, Liu Peng, Dongsheng Li, Fu Yuanguang, Dunfu Shi
Publikováno v:
Annals of Nuclear Energy. 152:107986
The direct whole core calculation is applied on Cobalt-59 activation calculation. The coupled neutronics, thermal hydraulics and depletion calculation is conducted, where the neutronics is solved by the Monte Carlo code JMCT and the thermal hydraulic
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2c65f5ddf0040ce8019b3774b83899fd
https://doi.org/10.1016/j.anucene.2020.107986
https://doi.org/10.1016/j.anucene.2020.107986
Monte Carlo methods are widely used in simulation of the full-core reactor. They are usually adopted to deal with the geometry model based on the Constructive Solid Geometry. A visual modeling software for the automatic particle transport program, ca
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=od______8936::abe28adefc4a3bf44ae577059c97d9d9
http://hdl.handle.net/11025/29615
http://hdl.handle.net/11025/29615
