Results 131 to 140 of about 24,201 (184)

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 (New series), 2019
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.
Seyed Mohammad Hossein Mousakazemi, N. Ayoobian   +1 more
semanticscholar   +1 more source

Scaling of natural circulation in PWR systems

Nuclear Engineering and Design, 1991
Abstract This paper deals with the problem of scaling complex thermalhydraulic scenarios measured in experimental facilities which simulate Pressurized Water Reactor systems. Phenomena occurring during different phases of natural circulation between the core and the steam generators are considered. The experimental data obtained in some integral test
D'AURIA, FRANCESCO SAVERIO, GALASSI G. M., VIGNI P., CALASTRI A.   +3 more
openaire   +2 more sources

Studies on the Use of Thorium in PWR

2020
A study was taken up to assess the use of thorium in PWR type of lattice. The case study was done for the 17 × 17 square lattice fuel assembly (FA) of Westinghouse design used in modern PWRs namely AP1000 and EPR. This work describes some theoretical results obtained by loading thorium in oxide form as main fertile with either LEU or PWR grade ...
Devesh Raj, Umasankari Kannan
openaire   +1 more source

Distributed-parallel CFD computation for all fuel assemblies in PWR core

, 2020
To further understand and monitor the thermal–hydraulic (TH) status of large domain of pressurized water reactor (PWR) core, an applicable engineering approach with high efficiency and high spatial resolution is critical.
G. Chen, Jijun Wang, Zhijian Zhang, Zhaofei Tian, Lei Li, Huilun Kang, Yuguan Jin   +6 more
semanticscholar   +1 more source

Safety Assessment of Advanced PWR

2018 International Conference on Power Generation Systems and Renewable Energy Technologies (PGSRET), 2018
In the present study, safety assessment of advanced light water nuclear reactor has been performed using the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) methodology. This methodology is considered to be a tool to check the nuclear energy system (NES) sustainability in seven different areas. Out of these seven areas, one
Suhail Ali, Kamran Qureshi, Saira Gulfam, Sarim Ahmed Qamar, Rab Nawaz   +4 more
openaire   +1 more source

A Multiscale and Multiphysics PWR Safety Analysis at a Subchannel Scale

Nuclear science and engineering, 2020
A high-fidelity safety analysis method for pressurized water reactors (PWRs) is presented using a multiscale and multiphysics coupled code. Computational resolution of the conventional safety analysis can be greatly improved using this method in which ...
H. Yoon, I. Park, J. R. Lee, S. J. Lee, Y. J. Cho, S. Do, Hyunduck Cho, J. Jeong   +7 more
semanticscholar   +1 more source

ABAQUS analysis of the SiC cladding fuel rod behavior under PWR normal operation conditions

Journal of Nuclear Materials, 2019
Silicon Carbide (SiC) cladding is anticipated to be superior to zirconium-based cladding with regard to tolerating light water reactor (LWR) accidents, but it is also crucial that the cladding performance under normal operation conditions be well ...
Wei Li, K. Shirvan
semanticscholar   +1 more source

Control of the reactor core power in PWR using optimized PID controller with the real-coded GA

Annals of Nuclear Energy, 2018
Load following is an importance topic in the Nuclear Power Plants (NPPs). One of the conventional and simplest ways is the use of Proportional-Integral-Derivative (PID) controller. The reactor power is simulated based on the point kinetic model.
Seyed Mohammad Hossein Mousakazemi, N. Ayoobian, G. Ansarifar   +2 more
semanticscholar   +1 more source

Ensuring the possibility of using thorium as a fuel in a pressurized water reactor (PWR)

Nuclear Science and Techniques, 2021
M. M. Mohsen, M. Abdel‐Rahman, A. Galahom   +2 more
semanticscholar   +1 more source

Development and verification of PWR-core fuel management calculation code system NECP-Bamboo: Part I Bamboo-Lattice

Nuclear Engineering and Design, 2018
As the core calculation component of our fuel management calculation code system NECP-Bamboo, Bamboo-Core provides all functions required by fuel management calculation.
Yunzhao Li, Bin Zhang, Qingming He, Dongyong Wang, Hongchun Wu, Liangzhi Cao, W. Shen   +6 more
semanticscholar   +1 more source