Zobrazeno 1 - 10
of 19
pro vyhledávání: '"Shinian Peng"'
Autor:
Xiaoyu Wang, Zhifang Qiu, Shinian Peng, Jian Deng, Wei Zeng, Luguo Liu, Xilin Zhang, Xue Zhang, Yunfeng Xia, Mingjun Wang
Publikováno v:
Frontiers in Energy Research, Vol 12 (2024)
Reactor thermal-hydraulic codes can be categorized into system codes, sub-channel codes and CFD (computational fluid dynamics) codes according to the spatial discretization and simplification methods. As a traditional reactor system safety analysis c
Externí odkaz:
https://doaj.org/article/6ca8003fc0014e78831a4e7497e0c843
Publikováno v:
Frontiers in Energy Research, Vol 12 (2024)
The UMo-Al monolithic fuel element has a special failure mode of blistering on the cladding surface under high temperature and high burn-up conditions. In order to provide an auxiliary means for the safety analysis and failure limit formulation of th
Externí odkaz:
https://doaj.org/article/d6fc59b52f3048999e0a668c8a46bb38
Publikováno v:
Heliyon, Vol 9, Iss 3, Pp e13883- (2023)
As a form of clean energy, nuclear energy has unique advantages compared to other energy sources in the present era, where low-carbon policies are being widely advocated. The exponential growth of artificial intelligence (AI) technology in recent dec
Externí odkaz:
https://doaj.org/article/04f4c09d86e7411cadaf07e699e1170e
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 2, Pp 439-445 (2021)
In view of the complex geometric structure of the rod bundle channel and the limitation of the current CHF visualization experiment technology, it is very difficult to obtain the rod bundle CHF mechanism directly through the phenomenon of the rod bun
Externí odkaz:
https://doaj.org/article/5f47ec961d6b490fb62e196e6cc66dd1
Publikováno v:
Frontiers in Energy Research, Vol 9 (2021)
For a water cooled reactor, the key thermal-hydraulic parameters span a wide range corresponding to different CHF regimes. Under accident conditions, due to the flow regime transition and interchannel mixing effect, the corresponding CHF can transiti
Externí odkaz:
https://doaj.org/article/1809653fff02470f9afd2675e6067952
Autor:
Yaou Shen, Shinian Peng, Mingyu Yan, Yu Zhang, Jian Deng, Hongxing Yu, Daishun Huang, Zhongchun Li
Publikováno v:
Frontiers in Energy Research, Vol 9 (2021)
Lead-based liquid metals (LLMs) such as lead–bismuth eutectic (LBE) and lead, are currently the most interesting candidate coolants for fast reactors because of their excellent physical properties, which can improve safety and reduce costs. However
Externí odkaz:
https://doaj.org/article/cf3fc1cadc134d8189ccb805a30022b6
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2019 (2019)
A modified multiobjective self-adaptive differential evolution algorithm (MMOSADE) is presented in this paper to improve the accuracy of multiobjective optimization design in the nuclear power system. The performance of the MMOSADE is tested by the Z
Externí odkaz:
https://doaj.org/article/7df0959e8ee44970a3c286ffcb6e554b
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2019 (2019)
The Critical Heat Flux (CHF) prediction under high pressure condition, even close to the vicinity of the critical pressure of water, is an important issue. Although there are many empirical CHF correlations, most of them have covered the pressure und
Externí odkaz:
https://doaj.org/article/e96b6fc4e9924f948bfbbf8ec4e34c04
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 2, Pp 439-445 (2021)
In view of the complex geometric structure of the rod bundle channel and the limitation of the current CHF visualization experiment technology, it is very difficult to obtain the rod bundle CHF mechanism directly through the phenomenon of the rod bun
Publikováno v:
Frontiers in Energy Research, Vol 9 (2021)
For water cooled reactor, the key thermal-hydraulic parameters span a wide range corresponding to different CHF regimes. Under accident conditions, due to the flow patterns transition and interchannel mixing effect, the corresponding CHF can transfer