Results 171 to 180 of about 2,961,144 (192)

Corium retention for high power reactors by an in-vessel core catcher in combination with External Reactor Vessel Cooling

Nuclear Engineering and Design, 2004
Abstract If there were inadequate cooling during a reactor accident, a significant amount of core material could become molten and relocate to the lower head of the reactor vessel, as happened in the Three Mile Island Unit 2 (TMI-2) accident. If it is possible to ensure that the vessel lower head remains intact so that relocated core materials are ...
J.L. Rempe, D.L. Knudson, K.G. Condie, K.Y. Suh, F.-B. Cheung, S.-B. Kim   +5 more
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Experimental and Analytical Studies on the Penetration Integrity of the Reactor Vessel Under External Vessel Cooling

Nuclear Technology, 2004
Experimental and analytical studies on the penetration integrity of the reactor vessel have been performed to investigate the potential for reactor vessel failure during a severe accident in the Ad...
Rae-Joon Park, Kyoung-Ho Kang, Jong-Tae Kim, Ki-Young Lee, Sang-Baik Kim   +4 more
openaire   +1 more source

Limiting Factors for External Reactor Vessel Cooling

Nuclear Technology, 2005
The method of external reactor vessel cooling (ERVC) that involves flooding of the reactor cavity during a severe accident has been considered a viable means for in-vessel retention (IVR). For high-power reactors, however, there are some limiting factors that might adversely affect the feasibility of using ERVC as a means for IVR.
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Experimental and Analytical Studies on Penetration Integrity of the Reactor Vessel Under External Vessel Cooling

10th International Conference on Nuclear Engineering, Volume 2, 2002
Experimental and analytical studies on the penetration integrity of the reactor vessel in the APR (Advanced Power Reactor) 1400 have been performed under the condition of external vessel cooling in a severe accident. The objective of this study is to estimate failure or non-failure of the penetration including the ICI (In-Core Instrumentation) nozzle ...
Rae-Joon Park, Kyoung-Ho Kang, Jong-Tae Kim, Kil-Mo Koo, Sang-Baik Kim, Ki-Young Lee   +5 more
openaire   +1 more source

Thermal Behavior of the Reactor Vessel Penetration Under External Vessel Cooling During a Severe Accident

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, Rae-Joon Park, Jong-Tae Kim, Byung-Tae Min, Ki-Young Lee, Sang-Baik Kim   +5 more
openaire   +1 more source

The comprehensive analysis of coolability limits of passive external reactor vessel cooling under in-vessel retention

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, Xiao Yan, Shanfang Huang, Junchong Yu   +3 more
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External cooling of reactor vessels during severe accident

2009
Chapter 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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Computation of Solid Melting With Wall Boiling Under External Reactor Vessel Cooling

Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, 2018
The 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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1-D Two-phase Flow Investigation for External Reactor Vessel Cooling

Transactions of the Korean Society of Mechanical Engineers B, 2007
When 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, Rae-Joon Park, Young-Rho Cho, Sang-Baik Kim, Sin Kim, Kwang-Soon Ha   +5 more
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Effect of External Cooling on the Thermal Behavior of a Boiling Water Reactor Vessel Lower Head

Nuclear Technology, 1994
Flooding 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, V. K. Dhir, William E. Kastenberg   +2 more
openaire   +1 more source