Search Results - "Ternovykh, M Y" :: K.UTB vyhledávací portál

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Testing the multigroup, group and subgroup options of the CONSYST / ABBN-RF system on criticality calculations of fast reactor models with MNUP fuel

by Ternovykh, M Y, Bogdanova, E V
Published in Journal of physics. Conference series (01.11.2020)

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Calculation of the CPS effectiveness in the high-power fast neutron lead reactor with varying degrees of heterogeneity of the description of reactor model

by Ryzhov, S N, Ternovykh, M Y
Published in Journal of physics. Conference series (01.11.2018)

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Investigation of radiation levels in the region of fuel-transfer cask for transportation of spent fuel of light-water reactors

by Shorov, V Y, Ternovykh, M Y, Gerasimov, A S
Published in Journal of physics. Conference series (01.11.2020)

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Neutron-physical characteristics modeling of light water reactors critical corium slurry in water

by Ternovykh, M Y, Abdumalikov, H M, Ryzhov, S N
Published in Journal of physics. Conference series (01.11.2020)

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Influence of accounting the distribution parameters of the fuel assembly (FA) and dynamic operating characteristics on the fuel nuclide composition of a VVER-1000 spent fuel assembly (SFA)

by Albrek, M M, Ternovykh, M Y, Shorov, V Y
Published in Journal of physics. Conference series (01.11.2018)

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CORIUMSITY program code for the consequences analysis of a severe core melt accident

by Saldikov, I S, Bogdanova, E V, Pugachev, P A, Ryzhov, S N, Smirnov, A D, Ternovykh, M Y, Tikhomirov, G V
Published in Journal of physics. Conference series (01.11.2020)

Get full text

Journal Article

Testing the multigroup, group and subgroup options of the CONSYST / ABBN-RF system on criticality calculations of fast reactor models with MNUP fuel

Calculation of the CPS effectiveness in the high-power fast neutron lead reactor with varying degrees of heterogeneity of the description of reactor model

Investigation of radiation levels in the region of fuel-transfer cask for transportation of spent fuel of light-water reactors

Neutron-physical characteristics modeling of light water reactors critical corium slurry in water

Influence of accounting the distribution parameters of the fuel assembly (FA) and dynamic operating characteristics on the fuel nuclide composition of a VVER-1000 spent fuel assembly (SFA)

CORIUMSITY program code for the consequences analysis of a severe core melt accident

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