Results 151 to 160 of about 10,412 (178)

Comparison of the error-integral performance indexes in a GA-tuned PID controlling system of a PWR-type nuclear reactor point-kinetics model

Progress in Nuclear Energy, 2021
Abstract The control of a nuclear power plant is important due to its nonlinear dynamics. An optimized proportional–integral–derivative (PID) controller is a popular tool to this end. PID is tuned by various methods, including a genetic algorithm (GA). The quality and speed of GA optimization depend on the objective function as the performance index.
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Robust tuned PID controller with PSO based on two-point kinetic model and adaptive disturbance rejection for a PWR-type reactor

Progress in Nuclear Energy, 2019
Abstract Nonlinear systems such as nuclear reactor dynamics are associated with parametric uncertainties and stability conditions. These properties must be taken into account in controller design. In this paper, an effective and robust Proportional–Integral–Derivative (PID) controller is designed and tuned.
Seyed Mohammad Hossein Mousakazemi, Navid Ayoobian   +1 more
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Transuranium Elements Transmutation in VVER and PWR Type of Reactors

Proceedings of the Bulgarian Academy of Sciences
The expected renaissance of nuclear energy production puts the now postponed decision on long-term spent nuclear fuel handling on focus. In case of tripling the currently existing nuclear power generation of the countries that signed the relevant declaration on COP-28, Bulgaria among them, the high level radioactive elements of the spent nuclear fuel ...
Mladen Mitev, Kalin Filipov, Denitza Zgureva-Filipova, Ivan Andreev   +3 more
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Study on the reactor core barrel instantaneous characteristics in case of Loss of Coolant Accident (LOCA) scenarios for loop-type PWR

Nuclear Engineering and Design, 2017
Abstract The asymmetric pressure wave caused by Loss of Coolant Accident (LOCA) transients in multi-loop type Pressurized Water Reactor (PWR) leads to great shock to the reactor core barrel. The instantaneous shock causes severe damage to the reactor vessel structure integrity.
Mingjun Wang, Lianfa Wang, Jianping Jing, Xinli Gao, Suizheng Qiu, Wenxi Tian, G.H. Su   +6 more
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Combined numerical and experimental investigations of local hydrodynamics and coolant flow mass transfer in Kvadrat-type fuel assemblies of PWR reactors with mixing grids

Thermal Engineering, 2014
Results of research works on studying local hydrodynamics and mass transfer for coolant flow in the characteristic zones of PWR reactor fuel assemblies in case of using belts of mixing spacer grids are presented. The investigations were carried out on an aerodynamic rig using the admixture diffusion method (the tracer-gas method).
S. M. Dmitriev, O. B. Samoilov, A. E. Khrobostov, A. V. Varentsov, A. A. Dobrov, D. V. Doronkov, V. D. Sorokin   +6 more
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Development and Verification of a Computational Fluid Dynamics Model for a PWR-type Small Modular Reactor Subchannel

Nuclear Engineering and Design, 2023
Normando Perazzo Barbosa Souto, Claudio Luiz de Oliveira, Sergio de Oliveira Vellozo, Ronaldo Glicério Cabral   +3 more
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Effect of Break Size on Flow Instabilities in a PWR-type Small Modular Reactor

Transactions of the American Nuclear Society - Volume 121, 2019
M. Ishii, A. Khandelwal, Y. Lin, S. Wang
openaire   +1 more source

Evaluation of Thermal-Hydraulic Feasibility of PWR-Type Reduced Moderation Water Reactor (RMWR)

The proceedings of the JSME annual meeting, 2000
Fumimasa ARAYA, Hiroyuki YOSHIDA, Masatoshi KURETA, Akira OHNUKI, Hajime AKIMOTO   +4 more
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Bibliometric Review and Technical Summary of PWR Small Modular Reactors

Energies, 2023
Pablo Fernández-Arias, Diego Vergara, Álvaro Antón-Sancho   +2 more
exaly  

A study on the feasibility of using Uranium Nitride (UN) fuel in Pressurized water reactors (PWR)

AEJ - Alexandria Engineering Journal, 2023
Moustafa Aziz
exaly