Zobrazeno 1 - 10 of 20 pro vyhledávání: '"Xiaoyang Gaus-Liu"'
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Akademický článek
Design Features and Simulation of the New-Build HELOKA-US Facility for the Validation of the DEMO Helium-Cooled Pebble Bed Intermediate Heat Transport and Storage System
Autor: Xiaoyang Gaus-Liu, Evaldas Bubelis, Sara Perez-Martin, Bradut-Eugen Ghidersa, Wolfgang Hering
Publikováno v: Journal of Nuclear Engineering, Vol 3, Iss 4, Pp 461-472 (2022)
For the EU-DEMO Helium-Cooled Pebble Bed (HCPB) concept, an indirect coupled design (ICD) with a molten salt (MS) loop as an intermediate heat transport and storage system (IHTS) is considered for the conceptual design phase. The IHTS with an energy
Externí odkaz: https://doaj.org/article/82e9fb2d60824851ba11f566b3751c0b
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4
Ablation of a Solid Material by High Temperature Liquid Jet Impingement: An Application to Corium Jet Impingement on a Sfr Core-Catcher
Autor: Thomas Cron, Nicolas Rimbert, Alexandre Lecoanet, B. Fluhrer, Frédéric Payot, Michel Gradeck, Xiaoyang Gaus-Liu, Christophe Journeau
Publikováno v: Journal of Nuclear Engineering and Radiation Science
Journal of Nuclear Engineering and Radiation Science, 2021, ⟨10.1115/1.4051448⟩
Journal of Nuclear Engineering and Radiation Science, ASME, 2021, ⟨10.1115/1.4051448⟩
This paper deals with ablation of a solid by a high temperature liquid jet. This phenomenon is a key issue to maintain the vessel integrity during the course of a nuclear reactor severe accident with melting of the core. Depending on the course of su
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::690f63e46d669b88f328dd677f4668c2
https://hal.univ-lorraine.fr/hal-03312388
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5
Experimental Studies on Two-Layer Corium Heat Transfer in Light Water Reactor Lower Head in LIVE2D Facility
Autor: Xiaoyang Gaus-Liu, Thomas Cron, B. Fluhrer
Publikováno v: Nuclear technology, 206 (9), 1385-1396
Nuclear Technology
In-vessel melt retention (IVMR) is a promising strategy in severe accident management for light water reactors. This strategy is not only adopted in the VVER 440 or AP600 reactors, but also included in higher-power reactors around 1000 MW(electric),
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::fe8179e329b4f20e44b7cbef87109622
https://publikationen.bibliothek.kit.edu/1000120877/87391265
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6
Experimental and numerical investigation of molten corium behavior in lower head under external subcooling and boiling conditions
Autor: Xiaoyang Gaus-Liu, T. Hollands, A. Miassoedov, P. Pandazis
Publikováno v: Annals of Nuclear Energy. 120:888-895
The in-vessel melt retention by flooding the reactor vessel externally is regarded as an effective severe accident management (SAM) strategy. According to this strategy, the corium will be stabilized within the lower head, by transferring the decay h
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::614630a85c2291bb1da1a8182701fbfe
https://doi.org/10.1016/j.anucene.2018.06.020
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7
Improvement and evaluation of debris coolability analysis module in severe accident analysis code SAMPSON using LIVE experiment
Autor: Alexei Miassoedov, Nejdet Erkan, Xiaoyang Gaus-Liu, Hongyang Wei, Koji Okamoto
Publikováno v: Annals of Nuclear Energy. 100:65-72
The purpose of this work is to validate the debris coolability analysis (DCA) module in the severe accident analysis code SAMPSON by simulating the first steady stage of the LIVE-L4 test. The DCA module is used for debris cooling in the lower plenum
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::7d3f4556277fb7361a05e878ba4b30f8
https://doi.org/10.1016/j.anucene.2016.10.011
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8
Transient refractory material dissolution by a volumetrically-heated melt
Autor: Frank Kretzschmar, Alexei Miassoedov, Gilles Ratel, Jean Marie Seiler, Xiaoyang Gaus-Liu, Hervé Combeau
Publikováno v: Nuclear Engineering and Design
Nuclear Engineering and Design, Elsevier, 2014, 280, pp.420-428. ⟨10.1016/j.nucengdes.2014.09.025⟩
Nuclear Engineering and Design, 2014, 280, pp.420-428. ⟨10.1016/j.nucengdes.2014.09.025⟩
International audience; The present work addresses the question of corium ceramic interaction in a core catcher during a core-melt accident in a nuclear power plant. It provides an original insight into transient aspects concerning dissolution of ref
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::30896b631f2a9bddf35bbdb5308468ca
https://doi.org/10.1016/j.nucengdes.2014.09.025
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9
Influence of Boundary Conditions, Vessel Geometry, and Simulant Materials on the Heat Transfer of Volumetrically Heated Melt in a Light Water Reactor Lower Head
Autor: Alexei Miassoedov, Xiaoyang Gaus-Liu
Publikováno v: Journal of Nuclear Engineering and Radiation Science. 3
This study investigates heat transfer characters of a volumetrically heated melt pool in LWR lower plenum. Experimental restrictions on prediction reliability are discussed. These restrictions include cooling boundary conditions, vessel geometries, a
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::41de4c3071249752d895c09ef8496d8f
https://doi.org/10.1115/1.4035853
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