Zobrazeno 1 - 10
of 19
pro vyhledávání: '"Wenpei, Feng"'
Publikováno v:
Frontiers in Energy Research, Vol 12 (2024)
In order to improve the core power density of liquid metal reactors, narrow rectangular fuel assemblies are typically used, which have obvious advantages in heat transfer capacity. However, the flow and heat transfer characteristics in coolant passag
Externí odkaz:
https://doaj.org/article/9a3c67e60aed4520bdb51d96d2e65d4a
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 5, Pp 908-917 (2020)
Corrosion of structural materials presents a critical challenge in the use of lead-bismuth eutectic (LBE) as a nuclear coolant in an accelerator-driven system. By forming a protective layer on the steel surfaces, corrosion of steels in LBE cooled rea
Externí odkaz:
https://doaj.org/article/18cbd28012e84fbc9ecafbd871933527
Autor:
Xue, Zhang, Hongxing, Yu, Jian, Deng, Sijia, Du, Xiaoyu, Wang, Wenpei, Feng, Hu, Yanwei, Xu, Wanhai, Liu, Xiaojing
Publikováno v:
Frontiers in Energy Research; 2024, p1-9, 9p
Publikováno v:
Springer Proceedings in Physics ISBN: 9789819910229
MOOSE (Multiphysics Object-Oriented Simulation Environment) is a powerful finite element multi-physics coupling framework, whose object-oriented, extensive system is conducive to the development of various simulation tools. In this work, a full-core
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::14c6318dfece06cbe6149c12cd260d0e
https://doi.org/10.1007/978-981-99-1023-6_43
https://doi.org/10.1007/978-981-99-1023-6_43
Publikováno v:
Springer Proceedings in Physics ISBN: 9789819910229
Operating conditions in the liquid metal fast reactor, like higher power density, higher temperature gradient, and higher burnup, are more severe to the fuel rod comparing to the light water reactor. The integrity and safety of the fuel rod is very e
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f6ec0040b6ae12faf6d0f87fb6b3aa0f
https://doi.org/10.1007/978-981-99-1023-6_60
https://doi.org/10.1007/978-981-99-1023-6_60
Publikováno v:
Volume 7B: Thermal-Hydraulics and Safety Analysis.
In this study, a thermal-hydraulic analysis is carried out for the core of natural circulation lead-cooled fast reactor SNCLFR-100. Steady-state and transient analysis are performed with porous medium approach-based code TWOPORFLOW. In the steady-sta
Publikováno v:
Volume 15: Student Paper Competition.
Fuel plate performance under irradiation is an important topic for the research reactor. The fuel plate is expected to deform after a long-time operation, which is a threat to the reactor safety. In this research, irradiation behaviors like interacti
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 5, Pp 908-917 (2020)
Corrosion of structural materials presents a critical challenge in the use of lead-bismuth eutectic (LBE) as a nuclear coolant in an accelerator-driven system. By forming a protective layer on the steel surfaces, corrosion of steels in LBE cooled rea
Autor:
Wenpei Feng, Chong Qin, Kefang Zhang, Guangliang Yang, Weixiang Wang, Wenshun Duan, Rui Pan, Hongli Chen
Publikováno v:
SSRN Electronic Journal.