Results 11 to 20 of about 130 (115)
Science and Technology of Nuclear Installations, 2021 According to the characteristics of the reactor internal structure of nuclear power plants, the vibration of the secondary core support pillar in water can be modeled as the vibration of the cantilever beam structure under the action of transverse flow ...
Xiaowen Wang, Yixian Zhou
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Science and Technology of Nuclear InstallationsOn September 2021, Polish government declared that six pressurized water reactors with combined capacity of 6–9 GWe will be built by 2040 to reduce Poland’s reliance on coal. Due to the adopted schedule, construction of the first nuclear power plant will
Edyta Agata Macieja, Juyoul Kim
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Experimental and Numerical Studies of AP1000 Shield Building considering Fluid-Structure Interaction
Science and Technology of Nuclear Installations, 2022 The gravity cooling water tank is a remarkable structural feature of third-generation pressurized water reactor nuclear power plant. To investigate the influence of fluid-structure interaction (FSI) on the seismic response of the structure, this study ...
Zhi Zhang +3 more
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Optimization and performance of metafoundations for seismic isolation of small modular reactors
Computer-Aided Civil and Infrastructure Engineering, Volume 38, Issue 12, Page 1558-1582, August 2023., 2023 Abstract This paper aims to study the seismic mitigation of a typical nuclear small modular reactor (SMR) where extreme loading conditions are considered by the safe shutdown earthquake. For this purpose, to reproduce the main dynamic properties of the reactor's reinforced concrete system, a detailed structural model was synthetized, also taking into ...
Tugberk Guner +2 more
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International Journal of Energy Research, Volume 2023, Issue 1, 2023., 2023 The external reactor vessel cooling provides a means to stabilize the molten core inside the reactor vessel during the severe accident in nuclear power plants. For a credible evaluation of the chances of success of in‐vessel melt retention, one requires high‐fidelity predictions on the natural circulation flow around the reactor vessel and, in ...
Yeon-Gun Lee, Il Woong Park, Geng Chen
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Advancing Small Modular Reactor Technology Assessment in the Czech Republic, Egypt, and Poland
Science and Technology of Nuclear Installations, Volume 2023, Issue 1, 2023., 2023 This paper introduces the utilization of the International Atomic Energy Agency’s toolkit for reactor technology assessment (RTA) application to deploy small modular reactors (SMRs) in the Czech Republic, Egypt, and Poland. The increasing demand for clean energy has led to the prominence of small modular reactors (SMRs) in addressing global energy ...
Waad Saleh +4 more
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Science and Technology of Nuclear Installations, Volume 2022, Issue 1, 2022., 2022 The micro‐mechanical state at the crack front is one of the key factors affecting the stress corrosion cracking (SCC) growth behavior. The mechanical heterogeneity and residual stress in the dissimilar metal welded joint (DMWJ) induce the micro‐mechanical state at the crack front to become more complex.
Shun Zhang +5 more
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Fault Diagnosis to Nuclear Power Plant System Based on Time‐Series Convolution Neural Network
Wireless Communications and Mobile Computing, Volume 2022, Issue 1, 2022., 2022 Nuclear power plant (NPP) is a highly complex engineering system which has typical internal feedback and strong component coupling. With these features, most NPP systems have high risk of radioactive release, which makes it essential to perform fault detection (FD) to the NPP systems.
XianLing Li +7 more
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Experimental Research for CHF Sensitivity of Heat Flux Distribution under IVR Conditions
Science and Technology of Nuclear Installations, Volume 2022, Issue 1, 2022., 2022 In‐vessel retention (IVR) through external reactor vessel cooling (ERVC) is one of the most effective severe accident mitigation measures in the nuclear power plants. The most influential issues on the IVR strategy are in‐vessel core melt evolution, the heat fluxes imposed on the lower head, and the external cooling of reactor pressurized vessel (RPV).
Shilei Han +4 more
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Innovative Design of Compact Heavy‐Load Independent Transfer Device for Nuclear Engineering System
Science and Technology of Nuclear Installations, Volume 2022, Issue 1, 2022., 2022 The transportation of heavy equipment in nuclear engineering has always been the focus of engineers, especially those transfer devices with the characteristics of small geometric size and heavy load. According to this kind of compact heavy‐load transfer device and its engineering tasks, the core problems caused by excessive vertical and horizontal ...
Hao Wan +6 more
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