Results 21 to 30 of about 6,570 (105)
Modelling of Severe Accident and In‐Vessel Melt Retention Possibilities in BWR Type Reactor
Science and Technology of Nuclear Installations, Volume 2018, Issue 1, 2018., 2018 One of the severe accident management strategies for nuclear reactors is the melted corium retention inside the reactor pressure vessel. The work presented in this article investigates the application of in‐vessel retention (IVR) severe accident management strategy in a BWR reactor.
Mindaugas Valinčius +4 more
wiley +1 more source
Strategy Evaluation for Cavity Flooding during an ESBO Initiated Severe Accident
Science and Technology of Nuclear Installations, Volume 2018, Issue 1, 2018., 2018 Intentional depressurization and cavity flooding are two important measures in current severe accident management guidelines (SAMGs). An extreme scenario of an extended station blackout (ESBO), when electric power is unavailable for more than 24 hours, actually occurred in the Fukushima Daiichi accident and attracted lots of attention.
Nan Jiang +4 more
wiley +1 more source
Role of Passive Safety Systems in Chinese Nuclear Power Development
Science and Technology of Nuclear Installations, Volume 2009, Issue 1, 2009., 2009 Passive safety systems have been widely applied to advanced water‐cooled reactors, to enhance the safety of nuclear power plants. The ambitious program of the nuclear power development in China requires reactor concepts with high safety level. For the near‐term and medium‐term, the Chinese government decided for advanced pressurized water reactors with
X. Cheng +4 more
wiley +1 more source
CORIUM BEHAVIOR IN THE LOWER PLENUM OF THE REACTOR VESSEL UNDER IVR-ERVC CONDITION: TECHNICAL ISSUES [PDF]
Nuclear Engineering and Technology, 2012 Corium behavior in the lower plenum of the reactor vessel during a severe accident is very important, as this affects a failure mechanism of the lower head vessel and a thermal load to the outer reactor vessel under the IVR-ERVC (In-Vessel corium Retention through External Reactor Vessel Cooling) condition. This paper discusses the state of the art and
Rae-Joon Park +4 more
openaire +1 more source
In‐Vessel and Ex‐Vessel Corium Stabilization in Light Water Reactor
, 2018 Science and Technology of Nuclear Installations, Volume 2018, Issue 1, 2018.
Hwan Yeol Kim +3 more
wiley +1 more source
, 2022 Serum LNG (pg/mL) in TFV/LNG continuous IVR Users (n = 18) and in TFV/LNG interrupted IVR users IVR users (n = 17).
Nazita Yousefieh (751094) +18 more
core +1 more source
Failure simulation of nuclear pressure vessel under LBLOCA scenarios
Nuclear Engineering and TechnologyThis paper presents the finite element deformation and failure simulation of a typical Korean high-power reactor vessel under a severe accident characterized by large break loss of coolant (LBLOCA) with in-vessel retention of molten corium through ...
Eui-Kyun Park +4 more
doaj +1 more source
, 2005 In-vessel retention (IVR) of core melt is a key severe accident management strategy adopted by some operating nuclear power plants and proposed for some advanced light water reactors (ALWRs).
Yang, J. +3 more
core +1 more source
RANS Analysis of Turbulent Natural Convection in BALI Configuration for IVR-ERVC SAM Strategy
, 2022 MasterDuring severe accident, the relocation of molten core to the vessel lower head would progress to release decay heat that can threaten the vessel integrity if no effective cooling mechanism is provided.
Evidente, Ralph Carlo
core
Nuclear Engineering and TechnologyIn-vessel retention through external reactor vessel cooling (IVR-ERVC) is a severe accident management (SAM) strategy that has been adopted and used in many nuclear reactors such as AP1000, APR1400, and light water reactor etc.
Hyeongi Moon +3 more
doaj +1 more source