Results 41 to 50 of about 1,504 (160)
Dynamic Analysis of AP1000 Shield Building Considering Fluid and Structure Interaction Effects
Nuclear Engineering and Technology, 2016 The shield building of AP1000 was designed to protect the steel containment vessel of the nuclear reactor. Therefore, the safety and integrity must be ensured during the plant life in any conditions such as an earthquake.
Qiang Xu +4 more
doaj +1 more source
Thermal Science, 2020 The heat transfer performance of the spent fuel transport cask is inseparably related to the safety of the whole reprocessing system. In this study, we carried out the thermal analysis on the NAC-STC transport cask for AP1000 spent fuel assembly to evaluate the thermal performance of transport cask by the finite element method software ANSYS.
Shujian Tian +5 more
openaire +2 more sources
Evaluation of Passive Safety Injection System Performance Under Large Break LOCA for Qinshan PWR
Frontiers in Energy Research, 2021 In this work, a brand new passive safety injection system has been designed for the ocean-based Qinshan Phase I nuclear power plant to update and replace the traditional active ones. The passive safety injection system is made up of high pressure, medium
Xuesong Wang +3 more
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A Fuzzy Probability Algorithm for Evaluating the AP1000 Long Term Cooling System to Mitigate Large Break LOCA [PDF]
, 2015 Components of nuclear power plants do not always have historical failure data to probabilistically evaluate their reliability characteristics. To overcome this drawback, an alternative approach has been proposed by involving experts to qualitatively ...
Purba, J. H. (J)
core +3 more sources
The General Design and Technology Innovations of CAP1400
Engineering, 2016 The pressurized water reactor CAP1400 is one of the sixteen National Science and Technology Major Projects. Developed from China's nuclear R&D system and manufacturing capability, as well as AP1000 technology introduction and assimilation, CAP1400 is an ...
Mingguang Zheng +5 more
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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 +4 more
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Nuclear Power: a Hedge against Uncertain Gas and Carbon Prices? [PDF]
, 2006 High fossil fuel prices have rekindled interest in nuclear power. This paper identifies specific nuclear characteristics making it unattractive to merchant generators in liberalised electricity markets, and argues that non-fossil fuel technologies have ...
David M. Newbery +4 more
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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 +6 more
wiley +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
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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
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