Results 271 to 280 of about 5,445,549 (348)
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, 2020
The Pressurized Water Reactor (PWR) based Small Modular Reactors (SMRs) are best suited to perform load-following operation because of their inherent self-stabilizing and self-regulating characteristics.
D. Bose +3 more
semanticscholar +1 more source
The Pressurized Water Reactor (PWR) based Small Modular Reactors (SMRs) are best suited to perform load-following operation because of their inherent self-stabilizing and self-regulating characteristics.
D. Bose +3 more
semanticscholar +1 more source
Annals of Nuclear Energy, 2019
This paper presents the multi-objective optimization of control parameters for a pressurized water reactor (PWR) pressurizer using a genetic algorithm.
Pengfei Wang, Xu Yan, Fuyu Zhao
semanticscholar +1 more source
This paper presents the multi-objective optimization of control parameters for a pressurized water reactor (PWR) pressurizer using a genetic algorithm.
Pengfei Wang, Xu Yan, Fuyu Zhao
semanticscholar +1 more source
Annals of Nuclear Energy, 2020
Power level control is important in nuclear power plants, and some dynamic parameters depend on the output power. One of the popular controllers is proportional–integral–derivative (PID), that the researchers are interested in tuning its gains.
Seyed Mohammad Hossein Mousakazemi
semanticscholar +1 more source
Power level control is important in nuclear power plants, and some dynamic parameters depend on the output power. One of the popular controllers is proportional–integral–derivative (PID), that the researchers are interested in tuning its gains.
Seyed Mohammad Hossein Mousakazemi
semanticscholar +1 more source
, 2020
In this paper, the development process of sub-channel code was described in detail, and some widely approved sub-channel codes were comprehensively reviewed, such as COBRA, FLICA, CORTH, and ASSERT applying to the commercial nuclear power plants ...
Jian Deng +6 more
semanticscholar +1 more source
In this paper, the development process of sub-channel code was described in detail, and some widely approved sub-channel codes were comprehensively reviewed, such as COBRA, FLICA, CORTH, and ASSERT applying to the commercial nuclear power plants ...
Jian Deng +6 more
semanticscholar +1 more source
Tribocorrosion in Pressurized Water Reactors
2013Most of the metallic alloys employed in pressurized water reactors (PWRs) have passivating properties that allow them to withstand relatively aggressive environmental conditions such as high temperatures, high pressure, and water-based coolants containing boric acid and lithium hydroxide.
Walter-John Chitty, Carole Falcand
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Automatic Reactor Power Control for a Pressurized Water Reactor
Nuclear Technology, 1993An automatic reactor power control system is presented for a pressurized water reactor (PWR). The associated reactor control strategy is called mode K.' The new system implements a heavy-worth bank dedicated to axial shape control, independent of the existing regulating banks.
Jung-In Choi, Yung-Joon Hah, Un-Chul Lee
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, 2020
Low cycle fatigue behavior of 316LN stainless steel (SS), 304 SS and 308L weld metal was investigated in air and high-temperature pressurized water environment. The effects of mechanical factors and environmental factors on fatigue lives were considered.
Ji-Bo Tan +8 more
semanticscholar +1 more source
Low cycle fatigue behavior of 316LN stainless steel (SS), 304 SS and 308L weld metal was investigated in air and high-temperature pressurized water environment. The effects of mechanical factors and environmental factors on fatigue lives were considered.
Ji-Bo Tan +8 more
semanticscholar +1 more source
, 2020
Effect of surface treatments on microstructure and stress corrosion cracking (SCC) of 308 L weld metal in primary pressurized water reactor environment was evaluated by microstructure characterization and bent beam tests.
Li-Jin Dong +5 more
semanticscholar +1 more source
Effect of surface treatments on microstructure and stress corrosion cracking (SCC) of 308 L weld metal in primary pressurized water reactor environment was evaluated by microstructure characterization and bent beam tests.
Li-Jin Dong +5 more
semanticscholar +1 more source
Volume 1: Codes and Standards, 2011
This paper describes stress analysis and fracture mechanics work performed to assess boiling water reactor (BWR) and pressurized water reactor (PWR) nozzles located in the reactor pressure vessel (RPV) adjacent to the core beltline region. Various RPV nozzle geometries were investigated: 1. BWR recirculation outlet nozzle; 2.
Shengjun Sean Yin +3 more
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This paper describes stress analysis and fracture mechanics work performed to assess boiling water reactor (BWR) and pressurized water reactor (PWR) nozzles located in the reactor pressure vessel (RPV) adjacent to the core beltline region. Various RPV nozzle geometries were investigated: 1. BWR recirculation outlet nozzle; 2.
Shengjun Sean Yin +3 more
openaire +1 more source
Dynamic analysis of a pressurized water reactor
Annals of Nuclear Energy, 1976Abstract An apparent malfunction in a pressurized water reactor system has been investigated using fluctuation analysis. Both frequency-domain and time-domain analyses have been used and the results obtained by the two methods have been compared. The recording was performed by a relatively simple, cheap system giving high recording precision and the ...
R.F. Saxe, C.W. Mayo, T. Saxe
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