Results 11 to 20 of about 401 (227)
Computational and Experimental Research in Materials and Renewable Energy, 2023 System failure in nuclear reactors can cause degradation of a reactor core, allowing melting and relocation of the corium to the lower plenum in the nuclear reactor system.
Muhamad Irfan +3 more
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Numerical simulation on heat transfer of VVER core cather
He jishu, 2023 BackgroundThe core corium may melt through the reactor pressure vessel wall then lead to the failure of the second barrier during a serious accident. Core catcher can collect and cool the corium and prevent the development of severe accident.PurposeThis ...
ZHU Guangyu +4 more
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Frontiers in Energy Research, 2022 China Nuclear Power Engineering, Northwestern Polytechnical University, and Beijing Institute of Technology have undertaken a joint research work with the goal of developing corium retention containers for use in an innovative light-water reactor core ...
Xu Han +8 more
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Frontiers in Energy Research, 2022 During a severe accident in a nuclear reactor, the molten core—or corium—may be relocated into the reactor vessel’s lower plenum in case of core support plate failure.
Jules Delacroix +2 more
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Transient thermal analysis of IVR strategy under a LB-LOCA based on ASTEC code
International Journal of Advanced Nuclear Reactor Design and Technology, 2021 A Large-Break Loss of Coolant Accident (LB-LOCA) in a generic, 1000 MWe and 3-loop Chinese Pressurized Water Reactor (PWR) with the In-Vessel corium Retention (IVR) strategy was simulated by using ASTEC V2.1.1.
Peng Chen +6 more
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Experimental Study on Stratification Morphology of the Molten Pool During Severe Accident
Frontiers in Energy Research, 2021 Stratification morphology of a molten pool under severe reactor accident was investigated by the CESEF experimental facility. The experimental scale was 5,000 g, the atomic ratio of U/Zr was 1.5, the content of stainless steel was 10%, and the oxidation ...
Yang Li +5 more
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Uncertainty analysis of molten corium In-Vessel Retention under External Reactor Vessel Cooling
International Journal of Advanced Nuclear Reactor Design and Technology, 2023 External Reactor Vessel Cooling (ERVC) is a key measure to realize molten corium In-Vessel Retention (IVR). The uncertainty of severe accident in core leads to the uncertainty of molten pool parameters in lower head, which may threat the reliability of ...
Shihao Wu +6 more
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A simplified geometrical model for transient corium propagation in core for LWR with heavy reflector
EPJ Nuclear Sciences & Technologies, 2017 In the context of the simulation of the Severe Accidents (SA) in Light Water Reactors (LWR), we are interested on the in-core corium pool propagation transient in order to evaluate the corium relocation in the vessel lower head.
Saas Laurent +2 more
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Science and Technology of Nuclear Installations, 2020 In order to enhance the ability of severe accident mitigation for Pressurised Water Reactor (PWR), different kinds of severe accident mitigation strategies have been proposed.
Dekui Zhan +4 more
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Can a nanofluid enhance the critical heat flux if the recirculating coolant contains debris?
Nuclear Engineering and Technology, 2022 In-vessel corium retention (IVR) during external reactor vessel cooling (ERVC) is a key severe accident management strategy adopted in advanced nuclear power plants. The injection of nanofluids has been regarded as a means of enhancing CHF when using the
Jihoon Han, Giju Nam, Hyungdae Kim
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