Results 11 to 20 of about 4,813 (258)
Nuclear Engineering and Technology, 2018 Improved load-following capability is one of the most important technical tasks of a pressurized water reactor. Controlling the nuclear reactor core during load-following operation leads to some difficulties.
M. Zaidabadi nejad, G.R. Ansarifar
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Nuclear Engineering and Technology, 2018 Various controllers such as proportional–integral–derivative (PID) controllers have been designed and optimized for load-following issues in nuclear reactors. To achieve high performance, gain tuning is of great importance in PID controllers.
Seyed Mohammad Hossein Mousakazemi +2 more
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Nuclear Engineering and Technology, 2017 The Helically coiled tube Once-Through Steam Generator (H-OTSG) is a key piece of equipment for compact small reactors. The present study developed and verified a thermal–hydraulic design and performance analysis computer code for a countercurrent H-OTSG
Yaoli Zhang +3 more
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Applied Sciences, 2022 A preliminary derived concentration guideline level (DCGL) was calculated for the soil of the Wolsong nuclear power plant (NPP) (the first commercial pressurized heavy water reactor in South Korea) site using the RESRAD-ONSITE computational code.
Chung-Gi Kwon +2 more
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The Concept of the Heat Removal System of a High-Flux Research Reactor
Science and Technology of Nuclear Installations, 2022 Achieving high neutron fluxes in research pressurized water reactors is directly related to the intensity of the coolant flow through the core and the pressure in it, which provides an increased saturation temperature and a margin to critical heat flux ...
Vitaly Uzikov +2 more
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Fatigue Properties of Long-Term Thermally Aged Low-Alloy Steel
MetalsFatigue properties of low-alloy steels, LAS, are well defined in air and at the beginning of life. However, the potential influence from thermal ageing under conditions relevant for the nuclear industry is uncertain. In this study, the fatigue properties
Robert Magnusson +2 more
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Analysis of the flow distribution and mixing characteristics in the reactor pressure vessel
Nuclear Engineering and Technology, 2021 The analysis of the fluid flow characteristics in reactor pressure vessel is an important part of the hydraulic design of nuclear power plant, which is related to the structure design of reactor internals, the flow distribution at core inlet and the ...
L.L. Tong, L.Q. Hou, X.W. Cao
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Yuanzineng kexue jishuThe corrosion failure of key structural materials such as 316L and 690TT in the primary circuit of nuclear power plants will seriously threaten the safety and service life of nuclear equipment, and the risk cannot be ignored.
HOU Tao1, 2, 3, NIE Xuechao2, 3, YANG Shunlong4, MENG Xianbo2, 3, XU Shengwei3, WANG Chenglong1, CHEN Yinqiang4
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Nuclear Engineering and Technology, 2016 In this research, for the first time, a new optimization method, i.e., strength Pareto evolutionary algorithm II (SPEA-II), is developed for the burnable poison placement (BPP) optimization of a nuclear reactor core.
Rahman Gharari +3 more
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Yuanzineng kexue jishu, 2023 Compared with traditional large scale pressurized water reactor, the volume of the containment of small pressurized water reactor is small. During a loss of coolant accident (LOCA), the containment pressure of small pressurized water reactor rises ...
QIN Bitan;ZHAO Dihong;HONG Gang;LU Jiaming;ZHANG Yaoli
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