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A critical heat flux model for IVR-ERVC application based on the experimental observation
Annals of Nuclear EnergyKuang Bo, Tianbiao Yu
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Influences of some engineered factors on IVR-ERVC limits
Nuclear Engineering and Design, 2019Abstract In-vessel retention (IVR) through passive external reactor vessel cooling (ERVC) has been adopted as one of the key severe accident mitigation strategies for Chinese-designed large-scale advanced passive pressurized water reactor. From the view of thermal load effectiveness, critical heat flux (CHF) of reactor pressure vessel (RPV) out wall ...
Bo Kuang +4 more
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Evaluation of an IVR-ERVC strategy for a high power reactor using MELCOR 2.1
Annals of Nuclear Energy, 2017Abstract The IVR-ERVC (In-Vessel Retention of molten corium through External Reactor Vessel Cooling) is an effective severe accident management strategy for reducing the possibility of a reactor containment failure by terminating the severe accident progress inside a reactor. However, the technical applicability and feasibility of the IVR-ERVC design
Kukhee Lim +3 more
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A theoretical and experimental study on subcooled flow boiling under passive IVR-ERVC conditions
Annals of Nuclear Energy, 2020Abstract External reactor vessel cooling (ERVC) strategy has been used in China advanced passive nuclear power plant. For this concept, it is very important to remove the decay heat through two phase natural circulation flow between reactor pressure vessel (RPV) wall and insulation.
Fan Wang +3 more
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CFD simulation on critical heat flux of flow boiling in IVR-ERVC of a nuclear reactor
Nuclear Engineering and Design, 2016Abstract The effectiveness of in-vessel retention (IVR) by external reactor vessel cooling (ERVC) strongly depends on the critical heat flux (CHF). As long as the local CHF does not exceed the local heat flux, the lower head of the pressure vessel can be cooled sufficiently to prevent from failure.
Xiang Zhang +4 more
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An experimental study on natural circulation flow characteristics under passive IVR-ERVC conditions
Annals of Nuclear Energy, 2019Abstract In vessel retention (IVR) of molten core debris via water cooling at the external surface of the reactor vessel is an important severe accident management feature of advanced passive plants. During postulated severe accidents, the heat generated by the molten debris relocated to the lower head of reactor pressure vessel needs to be removed ...
Fan Wang +3 more
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CHF experiments using a 2-D curved test section with additives for IVR-ERVC strategy
Nuclear Engineering and Design, 2012Abstract This study describes critical heat flux (CHF) experiments using a 2-D curved test section with trisodium phosphate (TSP: Na 3 PO 4 ) and boric acid (BA: H 3 BO 5 ). The CHF values of TSP solution, BA solution, and TSP + BA solution were enhanced by as much as 50% for all experimental conditions except the condition of 150 mm radius with BA ...
Kim, TI Kim, Tae-Il +2 more
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