Zobrazeno 1 - 10
of 919
pro vyhledávání: '"WU Hongchun"'
Publikováno v:
Yuanzineng kexue jishu, Vol 58, Iss 3, Pp 528-538 (2024)
The research and development progress of NECP-MCX, a deep penetrating cross-scale radiation field analysis software independently developed by Xi'an Jiaotong University, is summarized. New methods and functions have been developed for new application
Externí odkaz:
https://doaj.org/article/76903c687f8a4b6980bf43ab168c3964
Publikováno v:
He jishu, Vol 47, Iss 7, Pp 070503-070503 (2024)
BackgroundThe quantification of uncertainty has become a common requirement in reactor physics analysis whilst the covariance data of nuclear data serves as the foundational data for conducting uncertainty quantification.PurposeThis study aims to dev
Externí odkaz:
https://doaj.org/article/5fb4e467c02c422eb04e61e122e0efff
Autor:
He Qingming, Zheng Qi, Li Jie, Huang Zhanpeng, Huang Jinlong, Qin Shuai, Shu Hanlin, Peng Heyu, Yang Xuran, Shen Jingwen, Guo Jiandi, Cao Liangzhi, Wu Hongchun
Publikováno v:
EPJ Nuclear Sciences & Technologies, Vol 10, p 14 (2024)
NECP-MCX is a Monte-Carlo particle-transport code developed by the Nuclear Engineering Computational Physics (NECP) Lab. of Xi’an Jiaotong University in 2018. The first version of NECP-MCX is focused on addressing the challenge of deep-penetration
Externí odkaz:
https://doaj.org/article/74c818289bd647f59ca1337ff3a19a0a
Publikováno v:
EPJ Web of Conferences, Vol 302, p 10001 (2024)
The capability of sensitivity coefficients calculation of keff and reaction rate ratios to Legendre moment of scattering angular distributions based on a fully continuous method has been developed in the Monte Caro code NECP-MCX. The sensitivity calc
Externí odkaz:
https://doaj.org/article/191f8adae3e446728a972fb057a34783
Publikováno v:
EPJ Web of Conferences, Vol 302, p 14001 (2024)
This paper analyses the count rate of the ex-core source-range detector for Unit 4, M310 Pressurized Water Reactor (PWR), at Fujian Fuqing Nuclear Power Co., Ltd (FQNPC). The analysis encompasses power states during Cycle 1 startup and Cycle 3 fuel u
Externí odkaz:
https://doaj.org/article/33a5f2e429ca4bebb0403d4beb9eaaec
Publikováno v:
EPJ Web of Conferences, Vol 302, p 09004 (2024)
This paper discusses the implementation of the Consistent Adjoint-Driven Importance Sampling-Deterministic Transport (CADISDXTRAN) method in NECP-MCX to speed up Monte Carlo simulations for neutron radiation shielding applications. It provides a brie
Externí odkaz:
https://doaj.org/article/cfac2fc767d0431aa63ae0b23c9fa082
Publikováno v:
He jishu, Vol 46, Iss 12, Pp 120604-120604 (2023)
BackgroundNECP-SARAX is a neutronics analysis code system for advanced reactors developed by the Nuclear Engineering Computational Physics Laboratory team of Xi'an Jiaotong University. In the past few years, a considerable amount of verification and
Externí odkaz:
https://doaj.org/article/9db2a9807efb4dfeb4922e4da4d8e54a
Publikováno v:
Yuanzineng kexue jishu, Vol 56, Iss 2, Pp 193-212 (2022)
With the rapid development of computer science and technology, numerical simulation has become one of scientific research methods after theory research and experiment research, and it is now playing a very important role in the R&D of nuclear reactor
Externí odkaz:
https://doaj.org/article/cae5fd9e1f6c4b2c95a21734a8d454dc
Publikováno v:
EPJ Web of Conferences, Vol 281, p 00015 (2023)
The fission yield data provided by the evaluated nuclear data files do not contain covariance information, which is not conducive to uncertainty analysis. To generate covariance information, the model parameters of the code GEF which describes the fi
Externí odkaz:
https://doaj.org/article/85c76f349e1b452a90a3781960eb7485
Publikováno v:
EPJ Web of Conferences, Vol 247, p 03007 (2021)
Owing to its ability to handle arbitrary geometry and high computation efficiency, subgroup method is a widely used resonance self-shielding method. Ordinarily, the subgroup parameters are generated from homogenous resonance integral tables, and then
Externí odkaz:
https://doaj.org/article/496464b7e419416d93b41406b4e3fd71