Results 141 to 150 of about 1,560 (162)
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Annals of Nuclear Energy, 2018
Abstract The induced two-phase natural circulation flow and the critical heat flux (CHF) on the outer surface of lower head are crucial factors for the assessment of the external reactor vessel cooling (ERVC) under in-vessel retention which is considered as an effective management strategy to mitigate the core degradation accident.
Qiang Hu +3 more
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Abstract The induced two-phase natural circulation flow and the critical heat flux (CHF) on the outer surface of lower head are crucial factors for the assessment of the external reactor vessel cooling (ERVC) under in-vessel retention which is considered as an effective management strategy to mitigate the core degradation accident.
Qiang Hu +3 more
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Nuclear Technology, 2004
Experimental and analytical studies on the thermal behavior of reactor vessel penetration have been performed under external vessel cooling during a severe accident in the Korean next-generation reactor APR1400. Two types of tests, SUS-EXT and SUS-DRY with and without external vessel cooling, respectively, have been performed using sustained heating by
Kyoung-Ho Kang +5 more
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Experimental and analytical studies on the thermal behavior of reactor vessel penetration have been performed under external vessel cooling during a severe accident in the Korean next-generation reactor APR1400. Two types of tests, SUS-EXT and SUS-DRY with and without external vessel cooling, respectively, have been performed using sustained heating by
Kyoung-Ho Kang +5 more
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1-D Two-phase Flow Investigation for External Reactor Vessel Cooling
Transactions of the Korean Society of Mechanical Engineers B, 2007When a molten corium is relocated in a lower head of a reactor vessel, the ERVC (External Reactor Vessel Cooling) system is actuated as coolant is supplied into a reactor cavity to remove a decay heat from the molten corium during a severe accident.
Jae-Cheol Kim +5 more
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External cooling of reactor vessels during severe accident
2009Chapter 16 is devoted to the so called external cooling of reactor vessels during severe accident. It is a technology allowing arresting the melt inside the vessel of some initial conditions are fulfilled. First the state of the art is presented. Then a brief description of the phenomenology leading to melt in the lower head is discussed: dry core ...
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Annals of Nuclear Energy, 2001
Abstract A consistent probabilistic approach is proposed to evaluate the feasibility of in-vessel retention of the molten corium through external reactor vessel cooling (IVR-ERVC) during severe accidents of pressurized water reactors (PWRs). By combining the results of Level-1 probabilistic safety assessment, a critical heat flux correlation, and ...
Park, JH Park, Jae Hong +3 more
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Abstract A consistent probabilistic approach is proposed to evaluate the feasibility of in-vessel retention of the molten corium through external reactor vessel cooling (IVR-ERVC) during severe accidents of pressurized water reactors (PWRs). By combining the results of Level-1 probabilistic safety assessment, a critical heat flux correlation, and ...
Park, JH Park, Jae Hong +3 more
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Computation of Solid Melting With Wall Boiling Under External Reactor Vessel Cooling
Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, 2018The solid wall convection melting physics is computed with coupling external boiling physics based on the volume-of-fluid model in the STAR-CCM+ code. A three-dimensional rectangular computational sample domain is used with 5.0 cm height, 4.0 cm width and 1.0 cm depth.
Hyuk-Jin Song, Jong Woon Park
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Effect of External Cooling on the Thermal Behavior of a Boiling Water Reactor Vessel Lower Head
Nuclear Technology, 1994Flooding of the drywell of a boiling water reactor (BWR) is one of many accident management strategies being proposed to manage severe accidents in light water reactors. The effect of external cooling on the thermal behavior of the BWR vessel lower head containing molten core material has been numerically investigated using a two-dimensional implicit ...
Hyunjae Park +2 more
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RELAP Simulation on Boiling and Flow Phenomena Under External Reactor Vessel Cooling Condition
18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 2010External reactor vessel cooling (ERVC) of the In-vessel retention (IVR) system is widely accepted as a feasible way to remove decay heat from the lower head of the reactor pressure vessel (RPV) under severe accident (SA) conditions. However, some issues relating to ERVC still need to be evaluated before its application, such as boiling and flow ...
Yongchun Li +4 more
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Journal of Nuclear Science and Technology, 2015
To confirm the feasibility of the gallium–water IVR-ERVCS (in-vessel retention-external reactor vessel cooling system), this paper focuses on the numerical simulation of severe accidents in APR 1400 using MARS-LMR (multidimensional analysis of reactor safety-liquid metal reactor).
Kang, Sarah +3 more
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To confirm the feasibility of the gallium–water IVR-ERVCS (in-vessel retention-external reactor vessel cooling system), this paper focuses on the numerical simulation of severe accidents in APR 1400 using MARS-LMR (multidimensional analysis of reactor safety-liquid metal reactor).
Kang, Sarah +3 more
openaire +2 more sources