Zobrazeno 1 - 10
of 16
pro vyhledávání: '"Thermal hydraulic and neutronics coupling"'
Autor:
Ye, Linrong1 (AUTHOR), Wang, Mingjun1 (AUTHOR), Wang, Xin'an1 (AUTHOR), Deng, Jian2 (AUTHOR), Xiang, Yan3 (AUTHOR), Tian, Wenxi1 (AUTHOR), Qiu, Suizheng1 (AUTHOR), Su, G. H.1 (AUTHOR)
Publikováno v:
Science & Technology of Nuclear Installations. 8/28/2020, p1-12. 12p.
Autor:
Linrong Ye, Mingjun Wang, Xin’an Wang, Jian Deng, Yan Xiang, Wenxi Tian, Suizheng Qiu, G. H. Su
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2020 (2020)
The thermal hydraulic and neutronics coupling analysis is an important part of the high-fidelity simulation for nuclear reactor core. In this paper, a thermal hydraulic and neutronics coupling method was proposed for the plate type fuel reactor core
Externí odkaz:
https://doaj.org/article/fd547f1a0c6643419e208b2d30a65e81
Autor:
Wang Xin'an, Guanghui Su, Wenxi Tian, Suizheng Qiu, Jian Deng, Mingjun Wang, Yan Xiang, Linrong Ye
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2020 (2020)
The thermal hydraulic and neutronics coupling analysis is an important part of the high-fidelity simulation for nuclear reactor core. In this paper, a thermal hydraulic and neutronics coupling method was proposed for the plate type fuel reactor core
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::e2804cbd6a8f63ca511ac84373b013ef
Advanced computational tools are applied to simulate a nuclear power plant (NPP) control rod assembly ejection (CRE) accident. The impact of these reactivity-initiated accidents (RIAs) on core reactivity behavior, 3D power distribution and stochastic
Publikováno v:
Biblioteca Digital de Teses e Dissertações da USPUniversidade de São PauloUSP.
Advanced computational tools are applied to simulate a nuclear power plant (NPP) control rod assembly ejection (CRE) accident. The impact of these reactivity-initiated accidents (RIAs) on core reactivity behavior, 3D power distribution and stochastic
Publikováno v:
Kerntechnik; Dec2024, Vol. 89 Issue 6, p741-754, 14p
Autor:
Zhao, Jian1 (AUTHOR), Chen, Zhenyue1 (AUTHOR), Tu, Jingqi1,2 (AUTHOR), Zhao, Yunmei1 (AUTHOR) yunmeizhao@tongji.edu.cn, Dong, Yiqun2 (AUTHOR) yunmeizhao@tongji.edu.cn
Publikováno v:
Energies (19961073). Dec2022, Vol. 15 Issue 23, p9053. 14p.
Autor:
Zhang, Qingyang1,2 (AUTHOR), Peng, Tianji3,4 (AUTHOR), Zhang, Guangchun1,2 (AUTHOR), Liu, Jie1,2 (AUTHOR), Guo, Xiaowei1,2 (AUTHOR), Gong, Chunye1,2 (AUTHOR), Yang, Bo1,2 (AUTHOR), Fan, Xukai3 (AUTHOR)
Publikováno v:
Science & Technology of Nuclear Installations. 9/24/2021, p1-16. 16p.
Publikováno v:
Nuclear Science & Techniques; Nov2023, Vol. 34 Issue 11, p1-25, 25p
Pressurized Water Reactors, Volume Three in the JSME Series on Thermal and Nuclear Power Generation, compiles the latest research on Pressurized Water Reactors (PWRs) into a very comprehensive reference, beginning with its history. The reader is then