Zobrazeno 1 - 10
of 15
pro vyhledávání: '"Yu.A. Zvonarev"'
Autor:
Yu. M. Semchenkov, Yu.A. Zvonarev
Publikováno v:
Physics of Atomic Nuclei. 82:1186-1193
The results of computational analysis of the application of in-vessel and ex-vessel melt retention strategies for VVER of different capacity is presented. The choice in favor of an in-vessel melt retention strategy for VVER-600 and an ex-vessel core
Publikováno v:
Nuclear Engineering and Design. 385:111407
This paper provides information on the development and validation of the MAVR-TA code. The MAVR-TA code is designed to simulate the fission products release from fuel and melt, and the transfer of fission products in the primary circuit and in the co
Publikováno v:
Nuclear Engineering and Design. 382:111377
This paper provides information on the models of the MAVR-TA code, associated with modeling of the fission products transport in the primary circuit and inside the containment. The paper provides information on the system of the equations which is so
Publikováno v:
Nuclear Engineering and Design. 272:224-236
The paper is devoted to extended ASTEC analyses of possible in-vessel retention (IVR) phenomena, based on simulation of main accident scenarios for VVER-1000 reactor design with the ASTEC 2.0 rev2 code. To reach the objective of the investigation, an
Autor:
Yu.A. Zvonarev, A. V. Chistyakova, Vladimir M. Zhukov, P. S. Chursin, Yu. A. Kuzma-Kichta, A. V. Lavrikov, L. T. Vasil'eva, Mikhail Shustov
Publikováno v:
Thermal Engineering. 61:210-213
We present the results from a study of heat transfer enhancement for bulk water boiling at atmospheric pressure on a surface with micro- and nanorelief, including a relief formed from silicon carbide and aluminum oxide nanoparticles. Horizontally ori
Autor:
E. V. Moiseenko, A. Volchek, A. S. Filippov, Yu.A. Zvonarev, N. P. Kiselev, D. F. Tsurikov, V.L. Kobzar, Valery F. Strizhov
Publikováno v:
Physics of Atomic Nuclei. 74:1845-1853
A brief description of the HEFEST-ULR code and numerical results for corium behavior in a core catcher for the VVER-1200 (NPP-2006 project) are presented. Physical, chemical, and thermal processes during corium pool formation and cooling in the core
Publikováno v:
Nuclear Engineering and Design. 232:97-109
The treatment of zirconium oxidation kinetics in severe accident (SA) codes has been the subject of many discussions and controversies in recent years. The main problem was the existence of several correlations which could lead to large differences i
Autor:
Michael Buck, S. Marguet, M.S. Veshchunov, A.V. Boldyrev, G. Schanz, K. Mueller, I. Kleinhietpass, J. P. Van Dorsselaere, Martin Steinbrück, Giacomino Bandini, C. Homann, A. Miassoedov, V.L. Kobzar, A. Caillaux, P. Chatelard, J.A.F. Benitez, Yu.A. Zvonarev, Juri Stuckert, B. Adroguer, G. Azarian, F. Bertrand, E. Virtanen, J. Birchley, N. Cocuaud, W. Krauss, D. Knocke, Wolfgang Hering, L. Belovsky, D. Bottomley, V. Vrtilkova, A. V. Goryachev, T.v. Berlepsch, L. Bellenfant, Zoltán Hózer, H. Plank
Publikováno v:
Nuclear Engineering and Design. 221:55-76
The core loss during a severe accident (COLOSS) project is a 3-year shared-cost action which started in February 2000. The project is concerned with the consequences that core degradation, occurring under severe accident conditions, may have on H 2 p
Publikováno v:
Nuclear Engineering and Design
Nuclear Engineering and Design, 2011, 241, pp.1055--1062. ⟨10.1016/j.nucengdes.2010.06.014⟩
Nuclear Engineering and Design, 2011, 241, pp.1055--1062. ⟨10.1016/j.nucengdes.2010.06.014⟩
ASTEC and ICARE/CATHARE computer codes, developed by IRSN (France) (the former with GRS, Germany), are used in RRC KI (Russia) for the analyses of accident transients on VVER-type NPPs. The latest versions of the codes were continuously improved and
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::9ca8461639c0338d21dc6ee4ce533670
https://hal.archives-ouvertes.fr/hal-02924802
https://hal.archives-ouvertes.fr/hal-02924802
Autor:
Yu.A. Zvonarev, Istvan Toth, Attila Aszódi, C. Vitanza, Gy. Hegyi, I. Trosztel, P. Junninen, V.L. Kobzar, Y Makihara, G.L. Horvath, Zoltán Hózer, M. Fogel, K. Trambauer, P Matejovic, J. Verpoorten, K.C. Wagner, Gábor Légrádi, V. Guillard, K. Pietarinen, N. Tricot, Ildiko´ Boros, E. Perez-Feró, A. Voltchek, A. Molnár, E. Slonszki, Imre Nagy, L. Perneczky, Cs. Győri, M. Barnak
Publikováno v:
Hózer, Z, Aszódi, A, Barnak, M, Boros, I, Fogel, M, Guillard, V, Győri, C, Hegyi, G, Horváth, G L, Nagy, I, Junninen, P, Kobzar, V, Légrádi, G, Molnár, A, Pietarinen, K, Perneczky, L, Makihara, Y, Matejovic, P, Perez-Ferò, E, Slonszki, E, Tóth, I, Trambauer, K, Tricot, N, Troszterl, I, Verpoorten, J, Vitanza, A, Voltchek, K, Wagner, K C & Zvonarev, Y 2010, ' Numerical analyses of an ex-core fuel incident : Results of the OECD-IAEA Paks Fuel Project ', Nuclear Engineering and Design, vol. 240, no. 3, pp. 538-549 . https://doi.org/10.1016/j.nucengdes.2009.09.031
Nuclear Engineering and Design
Nuclear Engineering and Design, 2010, 240 (3), pp.538-549. ⟨10.1016/j.nucengdes.2009.09.031⟩
Nuclear Engineering and Design
Nuclear Engineering and Design, 2010, 240 (3), pp.538-549. ⟨10.1016/j.nucengdes.2009.09.031⟩
The OECD-IAEA Paks Fuel Project was developed to support the understanding of fuel behaviour in accident conditions on the basis of analyses of the Paks-2 incident. Numerical simulation of the most relevant aspects of the event and comparison of the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::4a0c084d5b18b160b63b8dbed137d420
https://cris.vtt.fi/en/publications/177c13bb-ed03-4c84-b4e4-7d855dc4b801
https://cris.vtt.fi/en/publications/177c13bb-ed03-4c84-b4e4-7d855dc4b801