Results 191 to 200 of about 401 (227)

Transient behavior and maximum heat flux ratios of two-layer corium pool

International Journal of Thermal Sciences, 2022
Kui Ge, Yukun Zhou, Shihao Wu
exaly   +2 more sources

Model development for the transient heat transfer in a corium pool

Nuclear Engineering and Design, 2021
Abstract A distributed parameter model has been proposed for the transient heat transfer calculation of IVR in this paper. The model, composed by the free convection model based on empirical correlations and the isothermal solidification model based on the moving boundary method, has been verified with the LIVE-L5L experiment.
Hao Yu, Minjun Peng, Nan Jiang, Hang Wang   +3 more
openaire   +1 more source

Oxidation kinetics of corium pool

Nuclear Engineering and Design, 2013
Abstract Experimental, theoretical and numerical studies of oxidation kinetics of an open surface corium pool have been reported. The experiments have been carried out within OECD MASCA program and ISTC METCOR, METCOR-P and EVAN projects. It has been shown that the melt oxidation is controlled by an oxidant supply to the melt free surface from the ...
Sulatsky, A. A., Smirnov, S. A., Granovsky, V. S., Khabensky, V. B., Krushinov, E. V., Vitol, S. A., Kotova, S. Yu., Fischer, M., Hellmann, S., Tromm, W., Miassoedov, A., Bottomley, D., Piluso, P., Barrachin, M.   +13 more
openaire   +3 more sources

Stratification and Heat Transfer of Molten Corium Pool for In-Vessel Retention

Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, 2020
Abstract In-vessel retention (IVR) consists in cooling the molten corium contained in the lower head of reactor vessel by natural convection and reactor cavity flooding. The general approach which is used to study IVR problems is a “bounding” approach which consists in assuming a specified corium pool stratification in the vessel and ...
Qingan Xiang, Jian Deng, Dahuan Zhu, Xiaoli Wu, Jinsheng Bi, Baowen Chen, Rong Cai, Libo Qian, Yugao Ma   +8 more
openaire   +1 more source

Theoretical Analysis for Corium Pool with Miscibility Gap

Nuclear Technology, 2003
A model is proposed describing the corium pool behavior with a material composition presenting a miscibility gap. The model is described in the first part of this paper, and the state of its validation is developed in the second part, against SIMECO experiments.
Jean-Marie Seiler, Angélique Fouquet, Karine Froment, Francoise Defoort   +3 more
openaire   +1 more source

Research on Natural Convection of Two-Layer Corium Pools

Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, 2020
Abstract As a promising mitigation strategy, In-vessel-retention (IVR) has been an important research focus in realms of nuclear safety analysis. For IVR analysis, it’s of importance to study the natural convection behaviors of the corium pool formed in the lower plenum of the reactor vessel.
Simin Luo, Hongping Sun, Yapei Zhang, Junmei Wu, Suizheng Qiu, Guanghui Su   +5 more
openaire   +1 more source

Influence of corium oxidation on fission product release from molten pool

Nuclear Engineering and Design, 2010
Qualitative and quantitative determination of the release of low-volatile fission products and core materials from molten oxidic corium was investigated in the EVAN project under the auspices of ISTC. The experiments carried out in a cold crucible with induction heating and RASPLAV test facility are described.
Bechta, S.V., Krushinov, E.V., Vitol, S.A., Khabensky, V.B., Kotova, S.Yu., Sulatsky, A.A., Gusarov, V.V., Almyashev, V.I., Ducros, G., Journeau, C., Bottomley, D., Clément, B., Herranz, L., Guentay, S., Trambauer, K., Auvinen, Ari, Bezlepkin, V.V.   +17 more
openaire   +3 more sources

An experimental study on layer inversion in the corium pool during a severe accident

Nuclear Engineering and Design, 2014
Abstract COSMOS (COrium configuration of the molten State in the MOst Severe accidents) tests using prototypic materials have been performed to investigate the layer inversion of the heavy metallic material in the corium pool. An induction heating method using a cold crucible was implemented for melting of the UO 2 –ZrO 2 –Zr–Fe mixture.
Kyoung-Ho Kang, Rae-Joon Park, Seong-Ho Hong, Seong-Wan Hong, Kwang Soon Ha   +4 more
openaire   +1 more source

Simulation on the Process of Core Molten Pool Formation and Corium Relocation in the Core Region

Volume 11: Mitigation Strategies for Beyond Design Basis Events, 2022
Abstract Accurately estimating the moment on which the core melt relocates to the lower head in severe accidents is crucial for evaluating the effectiveness of the In-Vessel Retention (IVR) strategy. However, the collapse and fragmentation of the fuel rods as well as the melting and re-solidification of the core material during the core ...
Xinhai Zhao, Peng Chen, Dongyu He, Ruhao Zhong   +3 more
openaire   +1 more source

Transient stratification modelling of a corium pool in a LWR vessel lower head

Nuclear Engineering and Design, 2015
Abstract In the context of light water reactor severe accidents analysis, this paper is focused on one key parameter of in-vessel corium phenomenology: the immiscible phases stratification and its impact on the heat flux distribution at the corium pool lateral boundary with the so-called focusing effect related to a “thin” top metal phase and the ...
R. Le Tellier, L. Saas, S. Bajard
openaire   +1 more source