Asmolov V.G. - article list

Author index, А, rticle author

Current state of system thermohydraulic codes and trends in their development abroad
Asmolov V.G., Blinkov V.N., Melikhov V.I., Melikhov O.I., Parfenov Yu.V., Emelyanov D.A., Kiselev A.E., Dolganov K.S.
Estimation of the density of U-Zr-Fe-O melts
Asmolov V.G., Zagryazkin V.N., Tsurikov D.F.
The interaction of nuclear reactor core melt with oxide sacrificial material of localization device for a nuclear power plant with water-moderated water-cooled power reactor
Asmolov V.G., Sulatskiy A.A., Beshta S.V., Granovskii V.S., Khabenskii V.B., Krushinov E.V., Vitol' S.A., Almjashev V.I., Gusarov V.V., Strizhev V.F.
The thermodynamics of $\mathrm{U}$ – $\mathrm{Zr}$ – $\mathrm{Fe}$ – $\mathrm{O}$ melts
Asmolov V.G., Zagryazkin V.N., Tsurikov D.F.
The existence of an immiscibility region in the $\mathrm{U}$ – $\mathrm{Zr}$ - $\mathrm{O}$ system
Asmolov V.G., Zagryazkin V.N., Astakhova E.V., Vishnevskii V.Yu., D'yakov E.K.
The density of $\mathrm{UO}_2$ – $\mathrm{ZrO}_2$ alloys
Asmolov V.G., Zagryazkin V.N., Astakhova E.V., Vishnevskii V.Yu., D'yakov E.K., Kotov A.Yu., Repnikov V.M.

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