Results 11 to 20 of about 8,520 (102)
Fuel–Coolant Interaction Visualization Test for In-Vessel Corium Retention External Reactor Vessel Cooling (IVR-ERVC) Condition [PDF]
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
doaj +3 more sources
Feasibility of flooding the reactor cavity with liquid gallium coolant for IVR-ERVC strategy
Nuclear Engineering and Design, 2013 Abstract In this paper, a new approach replacing the ERVC coolant by a liquid metal instead of water is studied to avoid the heat removal limit of CHF during boiling of water. As the flooding material, gallium is used in terms of the melting and boiling points.
Park, Seong Dae, Bang, In Cheol
openaire +3 more sources
Nuclear Engineering and TechnologyThe in-vessel retention through external reactor vessel cooling (IVR-ERVC) strategy is a key management strategy for early termination of a nuclear severe accident that can threaten the integrity of the reactor vessel.
Tae Hoon Lee +5 more
doaj +2 more sources
Evaluation of heat-flux distribution at the inner and outer reactor vessel walls under the in-vessel retention through external reactor vessel cooling condition [PDF]
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
doaj +2 more sources
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
doaj +2 more sources
Nuclear Engineering and Design, 2021 Abstract In the event of a core meltdown in a high-power reactor, the integrity of the reactor pressure vessel is presumably protected by severe accident mitigation systems such as in-vessel retention external reactor vessel cooling (IVR-ERVC). However, in the late phase of the accident, two possible locations on the RPV are prone to failure: the ...
Muritala Alade Amidu +4 more
openaire +2 more sources
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
doaj +1 more source
, 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
Dekui Zhan (12130140) +4 more
core +1 more source
Structural assessment of reactor pressure vessel under multi-layered corium formation conditions
Nuclear Engineering and Technology, 2015 External reactor vessel cooling (ERVC) for in-vessel retention (IVR) has been considered one of the most useful strategies to mitigate severe accidents.
Tae Hyun Kim +2 more
doaj +1 more source
Science and Technology of Nuclear Installations, Volume 2018, Issue 1, 2018., 2018 A steam explosion in a reactor cavity makes a mechanical load of the pressure pulse, which can result in a failure of the containment isolation. To prove the integrity of the containment during the ex‐vessel steam explosion, the effects of water conditions on a steam explosion have to be identified, and the impulse of a steam explosion has to be ...
Sang Ho Kim +3 more
wiley +1 more source