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[en] This paper gives briefly the characteristics of the RBMK reactors and describes the possible history of the accident of the reactor Tchernobyl-4
[fr]
Cet article donne assez rapidement les caracteristiques des reacteurs RBMK et decrit le scenario possible de l'accident du reacteur Tchernobyl no.4Journal
[en] Melting ultimately requires the heat production rate to exceed the removal rate. In a nuclear reactor this situation is initiated by either overpower or undercooling conditions. The latter is related to reduced cooling through loss of coolant flow or loss of coolant itself and may lead to general meltdown of the reactor core. Molten material is accumulated in the lower plenum of the reactor pressure vessel. The separation of phases results from different components densities of molten material. High temperature molten UO2 will slowly melt through the wall of RPV lower plenum. To avoid disruption of RPV, an instantaneous heat transfer is needed. To simulate the situation described above, general multiphase flow equations were developed. In order to describe the multiphase flow fully, the continuity, momentum and energy equations were derived using ensemble averaging rather then time or spatial averaging. Because of geometry of the lower plenum a spherical coordinate system was used, to enhance the accuracy of the calculation on the border. (author)
Source
Stritar, A.; Jencic, I. (Nuclear Society of Slovenia (Slovenia)) (eds.); European Nuclear Society (Switzerland); Ministry of Science and Technology of Slovenia, Ljubljana (Slovenia); Nuclear Power Plant Krsko (Slovenia); 562 p; ISBN 961-6207-04-0; 
; 1996; p. 237-244; 3. Regional Meeting: Nuclear Energy in Central Europe; Portoroz (Slovenia); 16-19 Sep 1996; Available from Nuclear Society of Slovenia, Jozef Stefan Institute, Jamova 39, Ljubljana (SI); 9 refs., 3 figs.
; 1996; p. 237-244; 3. Regional Meeting: Nuclear Energy in Central Europe; Portoroz (Slovenia); 16-19 Sep 1996; Available from Nuclear Society of Slovenia, Jozef Stefan Institute, Jamova 39, Ljubljana (SI); 9 refs., 3 figs.
[en] The severe core meltdown accident, which is not included as a design basis accident, has high consequence and low probability of occurrence and turns out to be a major risk factor in the overall risk assessment. The physical mechanisms of containment failure in core meltdown accidents are identified as steam explosion, debris bed coolability, hydrogen burning, steam spike and core-concrete interaction. The state of technology review is made for each subtopic about the previous and current researches for better understanding of the phenomenon. (Author)
Journal
Journal of the Korean Nuclear Society; ISSN 0372-7327; ; v. 17(1); p. 53-67
; v. 17(1); p. 53-67
[en] Short communication
Source
Deutsches Atomforum e.V., Bonn (Germany); Kerntechnische Gesellschaft e.V., Bonn (Germany); 700 p; ISSN 0720-9207; ; May 1997; p. 236-239; Inforum Verl; Bonn (Germany); Annual meeting on nuclear technology and membership meeting of Deutsches Atomforum e.V; Jahrestagung Kerntechnik (JK '97) und Mitgliederversammlung des Deutschen Atomforums e.V; Aachen (Germany); 13-15 May 1997
; May 1997; p. 236-239; Inforum Verl; Bonn (Germany); Annual meeting on nuclear technology and membership meeting of Deutsches Atomforum e.V; Jahrestagung Kerntechnik (JK '97) und Mitgliederversammlung des Deutschen Atomforums e.V; Aachen (Germany); 13-15 May 1997
[en] A survey is given of the development of probabilistic risk analyses from 1957 till now. Some of these risk studies, which have been performed in the past years, are discussed with emphasis on the risks, found in these studies, on nuclear melt-down and on the relative contribution of the most important initiating events. Only the contribution of internal events are taken into account. Finally some factors are indicated which could diminish the risk of a melt-down accident. (Auth.)
Source
Loon, A.J. van (ed.); Koninklijk Inst. voor Ingenieurs, Arnhem (Netherlands). Afdeling voor Kerntechniek; 195 p; ISBN 90-353-1001-2; ; 1987; p. 157-167; KIVI-Kerntechniek; Arnhem (Netherlands); How can the engineer minimize the risks of nuclear power plants?; The Hague (Netherlands); 20 Jan 1987; 8 refs.; 3 figs.; 1 table.
; 1987; p. 157-167; KIVI-Kerntechniek; Arnhem (Netherlands); How can the engineer minimize the risks of nuclear power plants?; The Hague (Netherlands); 20 Jan 1987; 8 refs.; 3 figs.; 1 table.
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