Results 41 to 50 of about 1,699,034 (145)

Research on rapid source term estimation in nuclear accident emergency decision for pressurized water reactor based on Bayesian network

Nuclear Engineering and Technology, 2021
Nuclear emergency preparedness and response is an essential part to ensure the safety of nuclear power plant (NPP). Key support technologies of nuclear emergency decision-making usually consist of accident diagnosis, source term estimation, accident ...
Guohua Wu, Jiejuan Tong, Liguo Zhang, Diping Yuan, Yiqing Xiao   +4 more
doaj   +1 more source

Methodology for Sensitivity Analysis of Homogenized Cross-Sections to Instantaneous and Historical Lattice Conditions with Application to AP1000^® PWR Lattice

Energies, 2021
In the two-step method for nuclear reactor simulation, lattice physics calculations are performed to compute homogenized cross-sections for a variety of burnups and lattice configurations. A nodal code is then used to perform full-core analysis using the
Dean Price, Thomas Folk, Matthew Duschenes, Krishna Garikipati, Brendan Kochunas   +4 more
doaj   +1 more source

Development and Application of CAP1400 Numerical Reactor System

Yuanzineng kexue jishu, 2022
Numerical reactor technology describes a variety of physical phenomena in the core of a nuclear reactor through highprecision, highresolution, high confidence and high fidelity numerical simulation method, based on highperformance calculation and ...
CAO Liangzhi;DENG Li;YANG Bo;LIU Zhouyu;LIU Peng;TANG Chuntao;SHI Dunfu;CHEN Ronghua;TIAN Wenxi;PENG Lianghui;WAN Chenghui;ZHANG Minwan;BI Guangwen;FEI Jingran;XU Xiaobei;LI Fan
doaj  

Research on the uncertainty problem of SDG fault diagnosis based on information flow

Frontiers in Energy Research, 2023
Accurate and complete diagnosis of nuclear accidents is the primary link to nuclear emergencies. The signed directed graph (SDG), as a common method of fault diagnosis, has good completeness.
Jiahui Huang, Jie Liu, Xiaohua Yang, Jiayu Ma, Hua Liu   +4 more
doaj   +1 more source

Effect of Air Temperature on Failure Prognosis of Passive Containment Cooling System in AP1000

Chemical Engineering Transactions, 2013
Passive Containment Cooling System is innovatively used in AP1000 reactor design in order to enhance the safety of new generation nuclear power plant.
Y. Yu, S. Wang, F. Niu
doaj   +1 more source

Establishing and Assessing of a Leak Collection System Analysis Method by Computational Fluid Dynamics

Modelling and Simulation in Engineering, Volume 2025, Issue 1, 2025.
Small leaks within a nuclear power plant can escalate into significant leaks, leading to plant shutdown and substantial losses if operational limits are exceeded. Thus, the demand for systems that can rapidly detect minor leaks is increasing. Current research seeks to address this need.
Dae Kyung Choi, Won Man Park, Woo-Shik Kim, Dong-Jin Euh, Tae-Soon Kwon, Choengryul Choi, Arpan Hazra   +6 more
wiley   +1 more source

Calculation and analysis of fast neutron fluence of pressure vessel in AP1000 reactor [PDF]

EPJ Web of Conferences
The structural integrity of the reactor pressure vessel plays an important role in the safe operation of AP1000 nuclear power plant. Radiation damage of fast neutrons is the main factor leading to pressure vessel material deterioration.
Wang Yue, Quan Guopiug, Yee Yeoh Eing, Zhu Cheng-lin, Yu Hui   +4 more
doaj   +1 more source

Steam Condensation Heat Transfer in the Presence of Noncondensable Gases (NCGs) in Nuclear Power Plants (NPPs): A Comprehensive Review of Fundamentals, Current Status, and Prospects for Future Research

International Journal of Energy Research, Volume 2024, Issue 1, 2024.
Efficient steam condensation is crucial for safe nuclear power plant (NPP) operations, preventing pressure buildup, overheating, and the release of radioactive materials. However, the presence of noncondensable gases (NCGs), such as air, nitrogen, hydrogen, or helium, can hinder the condensation process by creating a thermal resistance layer that ...
Samah A. Albdour, Yacine Addad, Nourah Alyammahi, Imran Afgan, Amin Shokrollahi   +4 more
wiley   +1 more source

A study on pressurizer cutting scenario for radiation dose reduction for workers using VISIPLAN

Nuclear Engineering and Technology, 2022
The operations in the design lifecycle of a nuclear power plant targeted to be decommissioned lead to neutron activation. Operations in the decommissioning process include cutting, decontamination, disposal, and processing.
Hak Yun Lee, Sun Il Kim, Jong Soon Song
doaj   +1 more source

Neutronic Analysis of Accident‐Tolerant Cladding Materials in 3D Full Core BEAVRS PWR Benchmark Using OpenMC Code

International Journal of Energy Research, Volume 2024, Issue 1, 2024.
After the Fukushima Daiichi nuclear accident in 2011, the performance of nuclear fuel during accidents became a matter of great concern. To address this, a new type of fuel technology called accident‐tolerant fuel (ATF) has been developed with the goal of enhancing the ability of light water reactors (LWRs) to withstand severe accident conditions. Iron‐
Khalid A. Alamri, Meshari M. Alqahtani, Abdullah S. Alomari, Abdullah I. Almarshad, Andrey Kuzmin   +4 more
wiley   +1 more source