Results 151 to 160 of about 1,560 (162)

Flow analyses using RELAP5/MOD3 code for OPR1000 under the external reactor vessel cooling

Annals of Nuclear Energy, 2006
Abstract External reactor vessel cooling (ERVC) is considered as one of the most promising severe accident management strategies for an in-vessel corium retention (IVR). Heat removal capacity and water availability at the vessel outer surface can be key factors determining the success of ERVC measures.
Kang, KH Kang, Kyoung-Ho, Park, RJ Park, Rae-Joon, Kim, SB Kim, Sang-Baik, Kim, HD Kim, Hee-Dong, Chang, SH Chang, Soon-Heung   +4 more
openaire   +2 more sources

Numerical study on ICI nozzle ejection of external vessel cooling reactors under severe accident conditions

International Journal of Precision Engineering and Manufacturing, 2017
This study aims to develop a safety analysis methodology through which the integrity of both the lower head and the in-core instrumentation (ICI) nozzles of an external vessel-cooling reactor in nuclear power plants can be verified through finite element analyses.
Ji Hoon Bae, Jong Rae Cho, Kwang Hyun Bang   +2 more
openaire   +1 more source

Flow boiling CHF enhancement in an external reactor vessel cooling (ERVC) channel using graphene oxide nanofluid

Nuclear Engineering and Design, 2013
Abstract External reactor vessel cooling for in-vessel retention of corium is an important concept to mitigate the consequences of a severe accident by flooding the reactor cavity. Although this system has some merits, it is restricted by the capacity of heat removal through the nucleate boiling on the outer surface of the reactor. In this study, the
Park, Seong Dae, Bang, In Cheol
openaire   +2 more sources

Analytical evaluation of two-phase natural circulation flow characteristics under external reactor vessel cooling

Annals of Nuclear Energy, 2009
This work proposes an analytical method of evaluating the effects of design and operating parameters on the low-pressure two-phase natural circulation flow through the annular shaped gap at the reactor vessel exterior surface heated by corium (molten core) relocated to the reactor vessel lower plenum after loss of coolant accidents.
openaire   +1 more source

Numerical study of thermal-hydraulic and structural parameters effects on CHF in subcooled forced convection flow during external reactor vessel cooling

Progress in Nuclear Energy, 2023
Yu Liu, Deqi Chen
exaly  

Numerical study of in-vessel retention under the gallium–water external reactor vessel cooling system using MARS-LMR

Journal of Nuclear Science and Technology, 2016
In Guk Kim, In Cheol Bang
exaly  

Thermal-fluid assessment of the design options for reactor vessel cooling in a prismatic core VHTR

Annals of Nuclear Energy, 2010
Min-Hwan Kim, Nam-Il Tak, Hong-Sik Lim   +2 more
exaly  

Features of heat and deformation behavior of a VVER-600 reactor pressure vessel under conditions of inverse stratification of corium pool and worsened external vessel cooling during the severe accident. Part 1. The effect of the inverse melt stratification and in-vessel top cooling of corium pool on the thermal loads acting on VVER-600’s reactor pressure vessel during a severe accident

Nuclear Engineering and Design, 2018
Vladimir Loktionov
exaly  

Numerical approach to study the thermal-hydraulic characteristics of Reactor Vessel Cooling system in sodium-cooled fast reactors

Progress in Nuclear Energy, 2019
Dalin Zhang, Shibao Wang, Yapei Zhang
exaly  

Computational study of the mixed cooling effects on the in-vessel retention of a molten pool in a nuclear reactor

Journal of Mechanical Science and Technology, 2004
Chang Hyun Sohn, Sohn Chang Hyun
exaly