Results 1 to 10 of about 83 (60)
Nuclear Engineering and Technology, 2015 Background: A numerical simulation was carried out to investigate the difference between internal and external heat-flux distributions at the reactor vessel wall under in-vessel retention through external reactor vessel cooling (IVR-ERVC). Methods: Total
Jaehoon Jung +3 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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Frontiers in Energy Research, 2022 Due to large uncertainty, the effectiveness of in-vessel retention (IVR) with external reactor vessel cooling (ERVC) for high-power reactors cannot be fully demonstrated during the transient process. To optimize the current IVR-ERVC strategy, the concept
Peng Chen +4 more
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In- and ex-vessel coupled analysis of IVR-ERVC phenomenon for large scale PWR
Annals of Nuclear Energy, 2015 AbstractAs a key severe accident management strategy for light water reactors (LWRs), in-vessel retention (IVR) through external reactor vessel cooling (ERVC) has been the focus of relevant studies for decades. However, previous studies only investigated the molten pool configurations considered to be in a final steady state mainly for reactors of such
Yue Jin, Xiaojing Liu
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Assessment of thermal safety margins for the IVR-ERVC strategy of the i-SMR using the CINEMA code
Nuclear Engineering and TechnologyIn-vessel corium retention with external reactor vessel cooling (IVR-ERVC) is a key severe accident mitigation strategy to prevent lower-head failure and retain fission products inside the reactor vessel. This study assesses the applicability of IVR-ERVC
Dong-Hun Shin +6 more
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Nuclear Engineering and Technology, 2016 A visualization test of the fuel–coolant interaction in the Test for Real cOrium Interaction with water (TROI) test facility was carried out. To experimentally simulate the In-Vessel corium Retention (IVR)- External Reactor Vessel Cooling (ERVC ...
Young Su Na +3 more
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Yuanzineng kexue jishu, 2022 External reactor vessel cooling (ERVC) is one of the important severe accident mitigation strategies to achieve in-vessel retention(IVR) of melt core debris under severe accident conditions.
HE Yihai;WANG Gang;KUANG Bo;LUO Yuejian;WU Xiaoli
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MATERIAL CONSTITUTIVE MODELING OF NUCLEAR PRESSURE VESSEL STEEL FOR IVR-ERVC SIMULATION
The Proceedings of the International Conference on Nuclear Engineering (ICONE), 2023 Eui-Kyun Park, Yun-Jae Kim
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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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Influence of an in-vessel debris bed on the heat load to a reactor vessel under an IVR condition
Nuclear Engineering and Technology, 2023 We measured the heat load to a reactor vessel with and without the in-vessel debris bed under an IVR-ERVC condition. Mass transfer methodology was adopted based on heat and mass transfer analogy to achieve high Ra′H of order ∼1015 with compact test rigs.
Joon-Soo Park +2 more
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