Natural convection of melted core at the bottom of nuclear reactor vessel in a severe accident
2017; Wiley; Volume: 42; Issue: 1 Linguagem: Inglês
10.1002/er.3893
ISSN1099-114X
AutoresHae-Kyun Park, Su-Hyeon Kim, Bum-Jin Chung,
Tópico(s)Nuclear Materials and Properties
ResumoInternational Journal of Energy ResearchVolume 42, Issue 1 p. 303-313 SPECIAL ISSUE PAPER Natural convection of melted core at the bottom of nuclear reactor vessel in a severe accident Hae-Kyun Park, Hae-Kyun Park orcid.org/0000-0002-9120-0483 Department of Nuclear Engineering, Kyung Hee University, 1732 Deogyeong-daero, Giheung-gu, Yongin-si, Gyeonggi-do, 17104 South KoreaSearch for more papers by this authorSu-Hyeon Kim, Su-Hyeon Kim orcid.org/0000-0002-3289-0314 Department of Nuclear Engineering, Kyung Hee University, 1732 Deogyeong-daero, Giheung-gu, Yongin-si, Gyeonggi-do, 17104 South KoreaSearch for more papers by this authorBum-Jin Chung, Corresponding Author Bum-Jin Chung bjchung@khu.ac.kr orcid.org/0000-0002-1549-4483 Department of Nuclear Engineering, Kyung Hee University, 1732 Deogyeong-daero, Giheung-gu, Yongin-si, Gyeonggi-do, 17104 South Korea Correspondence Bum-Jin Chung, Department of Nuclear Engineering, Kyung Hee University, 1732 Deogyeong-daero, Giheung-gu, Yongin-si, Gyeonggi-do 17104, South Korea. Email: bjchung@khu.ac.krSearch for more papers by this author Hae-Kyun Park, Hae-Kyun Park orcid.org/0000-0002-9120-0483 Department of Nuclear Engineering, Kyung Hee University, 1732 Deogyeong-daero, Giheung-gu, Yongin-si, Gyeonggi-do, 17104 South KoreaSearch for more papers by this authorSu-Hyeon Kim, Su-Hyeon Kim orcid.org/0000-0002-3289-0314 Department of Nuclear Engineering, Kyung Hee University, 1732 Deogyeong-daero, Giheung-gu, Yongin-si, Gyeonggi-do, 17104 South KoreaSearch for more papers by this authorBum-Jin Chung, Corresponding Author Bum-Jin Chung bjchung@khu.ac.kr orcid.org/0000-0002-1549-4483 Department of Nuclear Engineering, Kyung Hee University, 1732 Deogyeong-daero, Giheung-gu, Yongin-si, Gyeonggi-do, 17104 South Korea Correspondence Bum-Jin Chung, Department of Nuclear Engineering, Kyung Hee University, 1732 Deogyeong-daero, Giheung-gu, Yongin-si, Gyeonggi-do 17104, South Korea. Email: bjchung@khu.ac.krSearch for more papers by this author First published: 20 September 2017 https://doi.org/10.1002/er.3893Citations: 5Read the full textAboutPDF ToolsRequest permissionExport citationAdd to favoritesTrack citation ShareShare Give accessShare full text accessShare full-text accessPlease review our Terms and Conditions of Use and check box below to share full-text version of article.I have read and accept the Wiley Online Library Terms and Conditions of UseShareable LinkUse the link below to share a full-text version of this article with your friends and colleagues. Learn more.Copy URL Share a linkShare onFacebookTwitterLinkedInRedditWechat Summary A hypothetical severe accident was investigated when nuclear fuels are melted. Experiments were performed for natural convection heat transfer of the melted core at the bottom of the reactor vessel. To achieve highly buoyant force, mass transfer experiment was adopted by using copper electroplating system based on the analogy concept. Mean and local Nusselt numbers were measured and compared for 2 different configurations of the melted core: 2-layer and 3-layer oxide pools. The phenomenological analysis was carried out comparing with 2 different oxide pool configurations of the present works and the existing studies. Heat ratio of the lower head to the top plate was affected by Prandtl number and geometrical difference. Compared with the existing studies, the Nu of lower head were about 40% lower, and those of the top plate were about 60% higher. The local Nusselt number ratio of the lower head gradually increased along the upper region and did not become affected by thermal conditions of the top plate. The local top plate Nusselt numbers for the 2D test rig were uniform, while those for the 3D test rig had steep slope with the highest Nusselt number at the center. Citing Literature Volume42, Issue1Special Issue: Progress in Novel Nuclear Energy TechnologiesJanuary 2018Pages 303-313 RelatedInformation
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