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V.I. Tarasov

Russian Academy of Sciences

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Featured researches published by V.I. Tarasov.

Nuclear Engineering and Design | 2006

Development of the mechanistic code MFPR for modelling fission-product release from irradiated UO2 fuel

M.S. Veshchunov; V.D. Ozrin; V.E. Shestak; V.I. Tarasov; R. Dubourg; G. Nicaise

Journal of Nuclear Materials | 2007

Mechanistic modelling of urania fuel evolution and fission product migration during irradiation and heating

M.S. Veshchunov; R. Dubourg; V.D. Ozrin; V.E. Shestak; V.I. Tarasov

Journal of Nuclear Materials | 2009

An advanced model for grain face diffusion transport in irradiated UO2 fuel. Part 1: Model formulation

M.S. Veshchunov; V.I. Tarasov

Journal of Nuclear Materials | 2013

Modelling of irradiated UO2 fuel behaviour under transient conditions

M.S. Veshchunov; V.I. Tarasov

Nuclear Engineering and Design | 2011

A new mechanistic code SFPR for modeling of single fuel rod performance under various regimes of LWR operation

M.S. Veshchunov; A.V. Boldyrev; V.D. Ozrin; V.E. Shestak; V.I. Tarasov

Journal of Nuclear Materials | 2009

An advanced model for grain face diffusion transport in irradiated UO2 fuel. Part 2: Model implementation and validation

V.I. Tarasov; M.S. Veshchunov

Nuclear Engineering and Design | 2015

Development of the advanced mechanistic fuel performance and safety code using the multi-scale approach

M.S. Veshchunov; A.V. Boldyrev; A.V. Kuznetsov; V.D. Ozrin; M.S. Seryi; V.E. Shestak; V.I. Tarasov; G. E. Norman; A. Yu. Kuksin; V. V. Pisarev; D.E. Smirnova; S.V. Starikov; V. V. Stegailov; A. V. Yanilkin

Nuclear Engineering and Design | 2014

Models for fuel porosity evolution in UO2 under various regimes of reactor operation

V.I. Tarasov; M.S. Veshchunov

TMS2013 Supplemental Proceedings | 2013

Development of the Mechanistic Fuel Performance and Safety Code SFPR Using the Multi‐Scale Approach

Veshchunov; A.V. Boldyrev; V.D. Ozrin; V.E. Shestak; V.I. Tarasov; G. E. Norman; A. Yu. Kuksin; V. V. Pisarev; D.E. Smirnova; S.V. Starikov; V. V. Stegailov; A. V. Yanilkin

Nuclear Engineering and Design | 2013

Distribution of fission product residual decay heat in stratified core melt of LWR and its influence on sidewall heat flux

V.D. Ozrin; V.I. Tarasov; A.S. Filippov; E.V. Moiseenko; O.V. Tarasov

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M.S. Veshchunov

Russian Academy of Sciences

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V.D. Ozrin

Russian Academy of Sciences

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V.E. Shestak

Russian Academy of Sciences

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A.V. Boldyrev

Russian Academy of Sciences

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A. V. Yanilkin

Russian Academy of Sciences

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A. Yu. Kuksin

Russian Academy of Sciences

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D.E. Smirnova

Russian Academy of Sciences

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G. E. Norman

Russian Academy of Sciences

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S.V. Starikov

Russian Academy of Sciences

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V. V. Pisarev

Russian Academy of Sciences

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