| Development of the mechanistic code MFPR for modelling fission-product release from irradiated UO2 fuel MS Veshchunov, VD Ozrin, VE Shestak, VI Tarasov, R Dubourg, ... Nuclear Engineering and Design 236 (2), 179-200, 2006 | 172 | 2006 |
| Mechanistic modelling of urania fuel evolution and fission product migration during irradiation and heating MS Veshchunov, R Dubourg, VD Ozrin, VE Shestak, VI Tarasov Journal of nuclear materials 362 (2-3), 327-335, 2007 | 95 | 2007 |
| Core loss during a severe accident (COLOSS) B Adroguer, F Bertrand, P Chatelard, N Cocuaud, JP Van Dorsselaere, ... Nuclear Engineering and Design 235 (2-4), 173-198, 2005 | 85 | 2005 |
| High-temperature oxidation and quench behaviour of Zircaloy-4 and E110 cladding alloys M Steinbrück, J Birchley, AV Boldyrev, AV Goryachev, M Grosse, TJ Haste, ... Progress in Nuclear Energy 52 (1), 19-36, 2010 | 76 | 2010 |
| On the theory of fission gas bubble evolution in irradiated UO2 fuel MS Veshchunov Journal of nuclear materials 277 (1), 67-81, 2000 | 74 | 2000 |
| Physico-chemical behavior of Zircaloy fuel rod cladding tubes during LWR severe accident reflood P Hofmann, V Noack, MS Veshchunov, AV Berdyshev, AV Boldyrev, ... Report FZKA 5846, 1997 | 67 | 1997 |
| Modelling of grain face bubbles coalescence in irradiated UO2 fuel MS Veshchunov Journal of nuclear materials 374 (1-2), 44-53, 2008 | 51 | 2008 |
| Development of the advanced mechanistic fuel performance and safety code using the multi-scale approach MS Veshchunov, AV Boldyrev, AV Kuznetsov, VD Ozrin, MS Seryi, ... Nuclear Engineering and Design 295, 116-126, 2015 | 47 | 2015 |
| Quench behavior of zircaloy fuel rod cladding tubes: small-scale experiments and modeling of the quench phenomena P Hofmann, A Miassoedov, L Steinbock, M Steinbrück, AV Berdyshev, ... Forschungszentrum Karlsruhe GmbH, 1999 | 47 | 1999 |
| A new approach to the Brownian coagulation theory MS Veshchunov Journal of aerosol science 41 (10), 895-910, 2010 | 46 | 2010 |
| An advanced model for intragranular bubble diffusivity in irradiated UO2 fuel MS Veshchunov, VE Shestak Journal of Nuclear Materials 376 (2), 174-180, 2008 | 44 | 2008 |
| ZrO2 dissolution by molten zircaloy and cladding oxide shell failure: new experimental results and modelling P Hofmann, J Stuckert, A Miassoedov, MS Veshchunov, AV Berdyshev, ... Forschungszentrum Karlsruhe GmbH, 1999 | 41 | 1999 |
| Model for evolution of crystal defects in UO2 under irradiation up to high burn-ups MS Veshchunov, VE Shestak Journal of Nuclear Materials 384 (1), 12-18, 2009 | 40 | 2009 |
| Dissolution of solid UO2 by molten zircaloy MS Veshchunov, P Hofmann Journal of nuclear materials 209 (1), 27-40, 1994 | 40 | 1994 |
| Modelling of hydrogen absorption by zirconium alloys during high temperature oxidation in steam MS Veshchunov, AV Berdyshev Journal of nuclear materials 255 (2-3), 250-262, 1998 | 37 | 1998 |
| Critical evaluation of uranium oxide dissolution by molten Zircaloy in different crucible tests MS Veshchunov, P Hofmann, AV Berdyshev Journal of nuclear materials 231 (1-2), 1-19, 1996 | 37 | 1996 |
| Modelling of irradiated UO2 fuel behaviour under transient conditions MS Veshchunov, VI Tarasov Journal of nuclear materials 437 (1-3), 250-260, 2013 | 36 | 2013 |
| Oxidation of B4C by steam at high temperatures: New experiments and modelling M Steinbrück, MS Veshchunov, AV Boldyrev, VE Shestak Nuclear engineering and design 237 (2), 161-181, 2007 | 35 | 2007 |
| A new mechanistic code SFPR for modeling of single fuel rod performance under various regimes of LWR operation MS Veshchunov, AV Boldyrev, VD Ozrin, VE Shestak, VI Tarasov Nuclear engineering and design 241 (8), 2822-2830, 2011 | 34 | 2011 |
| Modelling of Zr-O and U-Zr-O melts oxidation and new crucible tests MS Veshchunov, J Stuckert, AV Berdyshev FZKA, 2002 | 31 | 2002 |
