Results 11 to 20 of about 6,570 (105)

Experimental Research for CHF Sensitivity of Heat Flux Distribution under IVR Conditions

Science and Technology of Nuclear Installations, 2022
In-vessel retention (IVR) through external reactor vessel cooling (ERVC) is one of the most effective severe accident mitigation measures in the nuclear power plants.
Shilei Han, Pengfei Liu, Bo Kuang, Yanhua Yang   +3 more
doaj   +3 more sources

Numerical simulation on in-vessel molten corium behavior with external vessel cooling using smoothed particle hydrodynamics

Nuclear Engineering and Technology
The 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, Yeon-Gun Lee, Kukhee Lim, Yun-Jae Kim, So-Hyun Park, Eung Soo Kim   +5 more
doaj   +2 more sources

Coupled Analysis of Heat Transfer in a Molten Pool With Three-Layer Configuration

Frontiers in Energy Research, 2022
Understanding a reliable description of the heat transfer in the molten pool with three-layer configuration is inevitable for the design of severe accident mitigation measures in research reactors, such as IVR-ERVC.
Jian Deng, Dahuan Zhu, Yuejian Luo, Hongping Sun, Ming Zhang, Lili Liu, Qingan Xiang, Xiaoli Wu, Youyou Xu, Qingwen Xiong   +9 more
doaj   +1 more source

Heat transfer characteristics of single-layer and two-layer corium pool in elliptical lower head

International Journal of Advanced Nuclear Reactor Design and Technology, 2022
In this study, we investigated the characteristics of natural convection heat transfer of single-layer and two-layer corium pool in the elliptical lower head by the numerical method.
Y.P. Zhang, D.H. Zhu, K. Ge, Y.W. Wu, W.X. Tian, G.H. Su, S.Z. Qiu   +6 more
doaj   +1 more source

Effect of finned structure on critical heat flux (CHF) in downward-face pool boiling

Mechanical Engineering Journal, 2020
Critical heat flux (CHF) plays an important role as the upper limit of heat dissipation process during the in-vessel reactor external reactor vessel cooling (IVR-ERVC). IVR-ERVC is regarded as a very effective way to release the decay heat after the core
Kai WANG, Nejdet ERKAN, Koji OKAMOTO
doaj   +1 more source

Transient heat transfer and crust evolution during debris bed melting process in the hypothetical severe accident of HPR1000

Nuclear Engineering and Technology, 2023
In the late in-vessel phase of a nuclear reactor severe accident, the internal heat transfer and crust evolution during the debris bed melting process have important effects on the thermal load distribution along the vessel wall, and further affect the ...
Chao Lv, Gen Li, Jinchen Gao, Jinshi Wang, Junjie Yan   +4 more
doaj   +1 more source

Studies on Key Effect Factors of Natural Circulation Characteristics for Advanced PWR Reactor Cavity Flooding System

Science and Technology of Nuclear Installations, Volume 2020, Issue 1, 2020., 2020
In order to enhance the ability of severe accident mitigation for Pressurised Water Reactor (PWR), different kinds of severe accident mitigation strategies have been proposed. In‐Vessel Retention (IVR) is one of the important severe accident management means by External Reactor Vessel Cooling. Reactor cavity would be submerged to cool the molten corium
Dekui Zhan, Xinhai Zhao, Shaoxiong Xia, Peng Chen, Huandong Chen, Han Zhang   +5 more
wiley   +1 more source

DataSheet1_Research on Optimized Design of In-Vessel Retention–External Reactor Vessel Cooling Strategy and Negative Effect Assessment.pdf

, 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), Peng Chen (6514), Zijie Wu (8920853), Xinhai Zhao (5865773), Shaoxiong Xia (12130143)   +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, Seung Hyun Kim, Yoon-Suk Chang   +2 more
doaj   +1 more source

Analysis of Steam Explosion under Conditions of Partially Flooded Cavity and Submerged Reactor Vessel

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, Seong-Wan Hong, Rae-Joon Park, Arkady Serikov   +3 more
wiley   +1 more source