Results 31 to 40 of about 5,445,549 (348)
Nuclear Engineering and Technology, 2020 The objective of this study is to design a robust power control system for a small pressurized water reactor (PWR) to achieve stable power operations under conditions of external disturbances and internal model uncertainties.
Xu Yan +4 more
semanticscholar +1 more source
Multi-Scale Modelling of a Solar Reactor for the High-Temperature Step of a Sulphur-Iodine-Based Water Splitting Cycle [PDF]
, 2011 The 3-step sulphur-iodine-based thermochemical cycle for splitting water is considered. The high temperature step of the closed-material cycle consists of evaporation, decomposition, and reduction of sulphuric acid to SO2 using concentrated solar process
Roeb, Martin +7 more
core +2 more sources
MCNP model of a 17x17 pins Westinghouse pressurized water reactor fuel assembly.
, 2023 MCNP model of a 17x17 pins Westinghouse pressurized water reactor fuel assembly.
Nader M. Mohamed (16542007) +3 more
core +1 more source
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
doaj +1 more source
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
doaj +1 more source
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
doaj +1 more source
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
doaj +1 more source
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
doaj +1 more source
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
doaj
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
doaj +1 more source