Modeling of the corium crust of a stratified corium pool during severe accidents in light water reactors (English)
- New search for: Viot, L.
- New search for: Le Tellier, R.
- New search for: Peybernes, M.
- New search for: Viot, L.
- New search for: Le Tellier, R.
- New search for: Peybernes, M.
In:
Nuclear Engineering and Design
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368
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2020
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ISSN:
- Article (Journal) / Electronic Resource
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Title:Modeling of the corium crust of a stratified corium pool during severe accidents in light water reactors
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Contributors:
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Published in:
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Publisher:
- New search for: Elsevier B.V.
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Publication date:2020-08-10
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ISSN:
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DOI:
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Type of media:Article (Journal)
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Type of material:Electronic Resource
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Language:English
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Keywords:
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Source:
Table of contents – Volume 368
The tables of contents are generated automatically and are based on the data records of the individual contributions available in the index of the TIB portal. The display of the Tables of Contents may therefore be incomplete.
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Experimental correlation for critical heat flux in helical coilsHardik, B.K. / Prabhu, S.V. et al. | 2020
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Lifetime estimation of a BWR core shroud in terms of IGSCCBalachov, Iouri / Fekete, Balazs / Macdonald, Digby D. / Spencer, Benjamin et al. | 2020
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System code evaluation of near-term accident tolerant claddings during pressurized water reactor station blackout accidentsJin, Yue / Wu, Xu / Shirvan, Koroush et al. | 2020
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Modeling of the corium crust of a stratified corium pool during severe accidents in light water reactorsViot, L. / Le Tellier, R. / Peybernes, M. et al. | 2020
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Density stratification breakup by a vertical jet: Experimental and numerical investigation on the effect of dynamic change of turbulent schmidt numberAbe, Satoshi / Studer, Etienne / Ishigaki, Masahiro / Sibamoto, Yasuteru / Yonomoto, Taisuke et al. | 2020
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Thermal-hydraulic analysis of Al2O3 nanofluid as a coolant in Canadian supercritical water reactor by porous media approachSalehi, Danial / Jahanfarnia, Gholamreza / Zarifi, Ehsan et al. | 2020
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Numerical simulation of the open-pool reactor coolant system using a multi-domain approachCorzo, Santiago F. / Godino, Dario M. / Costa, Antonella L. / Reis, Patricia A.L. / Pereira, Claubia / Ramajo, Damian E. et al. | 2020
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Predication of wall shear stress of vertical upward co-current adiabatic air-water annular flow in pipesJu, Peng / Pan, Liang-ming / Yan, Yikuan / Zhu, Qingzi / He, Hui / Yang, Xiaohong / Ishii, Mamoru et al. | 2020
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Designs of control rods with strong absorption ability for small fast reactorsGuo, H. / Buiron, L. / Sciora, P. / Kooyman, T. et al. | 2020
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High temperature deformation behavior of Indian PHWR Calandria material SS 304LMohta, Keshav / Gupta, Suneel K. / Cathirvolu, Soupramanien / Jaganathan, Swaminathan / Chattopadhyay, J. et al. | 2020
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The effect of different turbulent flow on failure behavior in secondary loop of the pressurized water reactorHu, Y. / Zhao, L. / Lu, Y.H. / Shoji, T. et al. | 2020
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Physics study of block/prismatic-type HTGR design option for the Indonesian Experimental Power Reactor (RDE)Hartanto, Donny / Liem, Peng Hong et al. | 2020
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Nonlinear characteristics analysis of sodium flow measurement based on the principle of turbulent fluctuationYu, Xin-Long / Xu, Ke-Jun / Wu, Wen-Kai / Yan, Xiao-Xue / Huang, Ya et al. | 2020
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External surface temperature measurements for the heat transfer analysis of internally heated cylindrical clad-tubes subjected to external forced convection bulk water coolant thermal-hydraulic conditionsGovinder, K. / Slabber, J.F.M. / Meyer, J.P. et al. | 2020
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Effect of the flow approach angle on the dynamics of loosely-supported tube arraysElhelaly, Amro / Hassan, Marwan / Mohany, Atef / Eid Moussa, Soha et al. | 2020
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Editorial Board| 2020
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Whole-core transient analysis methodology for prismatic high temperature gas reactorsHuning, Alexander / Chandrasekaran, Sriram / Garimella, Srinivas et al. | 2020
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Reactor performance and safety characteristics of two-phase composite moderator concepts for modular high temperature gas cooled reactorsDuchnowski, Edward M. / Kile, Robert F. / Snead, Lance L. / Trelewicz, Jason R. / Brown, Nicholas R. et al. | 2020
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A review of research and development of supercritical carbon dioxide Brayton cycle technology in nuclear engineering applicationsWu, Pan / Ma, Yunduo / Gao, Chuntian / Liu, Weihua / Shan, Jianqiang / Huang, Yanping / Wang, Junfeng / Zhang, Dan / Ran, Xu et al. | 2020
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Surrogate modelling of transient stratified flow in a u-shaped pipeZimoń, Małgorzata J. / Skillen, Alex / Liu, Wendi / Sawko, Robert et al. | 2020
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Development of relocation model for debris particles in core disruptive accident analysis of sodium-cooled fast reactorTeng, Chunming / Zhang, Bin / Shan, Jianqiang / Zhang, Xisi / Cao, Yonggang et al. | 2020
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Risk of Japanese PWR plants by shutting off forced core cooling in an accident requiring safety injection systemYoshida, Yoshitaka et al. | 2020
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Radiative heat transfer in FLiBe molten salt participating medium in a vertical heated tube under forced and mixed convection laminar flowsAbou Dbai, Mohamed / Scarlat, Raluca O. / Trujillo, Mario F. et al. | 2020
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A unique molten salt reactor feature – The freeze valve system: Design, operating experience, and reliabilityChisholm, Brandon M. / Krahn, Steven L. / Sowder, Andrew G. et al. | 2020
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Neutronics and thermal-hydraulics coupling analysis using the FLUENT code and the RELAP5-3D code for a molten salt fast reactorMochizuki, Hiroyasu et al. | 2020
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Comparative analysis of reactor pressure vessel failure using two thermo-fluid-structure coupling approachesYu, Peng / Ma, Weimin et al. | 2020
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Development of a new spacer grid pressure drop model in rod bundle for the post-dryout two-phase flow regime during reflood transientsJin, Yue / Cheung, Fan-Bill / Shirvan, Koroush / Bajorek, Stephen M. / Tien, Kirk / Hoxie, Chris L. et al. | 2020