A.I. Radaev scite author profile

A.I. Radaev

5Publications

9Citation Statements Received

8Citation Statements Given

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Affiliations

Moscow Engineering Physics Institute, Dollezhal Research and Development Institute of Power Engineering

Publications

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Comparative validation of Monte Carlo codes for the conversion of a research reactor

Alferov

Radaev

Shchurovskaya

et al. 2015

Annals of Nuclear Energy

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This paper presents the calculation results of the set of test problems for a research reactor with a tube-type low enriched uranium (LEU, 19.7 w/o, U-9%Mo) fuel and oxide high enriched uranium (HEU, 90 w/o) fuel, a light water moderator, and a beryllium reflector. The static cases and the depletion problem were examined. Calculations were performed using continuous energy Monte Carlo codes: MCNP (+MCREB for burnup calculation), MCU-PTR, and SERPENT 2. The impact of the cross-section libraries used for a particular problem on the calculated results was investigated.

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Control rod calibration simulation using Monte Carlo code for the IRT-type research reactor

Shchurovskaya

Alferov

Geraskin

et al. 2016

Annals of Nuclear Energy

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Validation of the MCU-PTR computational model of beryllium poisoning using selected experiments at the IRT-T research reactor

Shchurovskaya

Alferov

Geraskin

et al. 2018

Annals of Nuclear Energy

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Transfer of the VVR-K Research Reactor to Low-Enrichment Uranium Fuel as a Basis for the Development and Adoption of VVR-KN Fuel Assemblies

et al. 2015

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Validation of deterministic and Monte Carlo codes for neutronics calculation of the IRT-type research reactor

Shchurovskaya¹,

Alferov²,

Geraskin³

et al. 2017

J. Phys.: Conf. Ser.

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A.I. Radaev

Comparative validation of Monte Carlo codes for the conversion of a research reactor

Control rod calibration simulation using Monte Carlo code for the IRT-type research reactor

Validation of the MCU-PTR computational model of beryllium poisoning using selected experiments at the IRT-T research reactor

Transfer of the VVR-K Research Reactor to Low-Enrichment Uranium Fuel as a Basis for the Development and Adoption of VVR-KN Fuel Assemblies

Validation of deterministic and Monte Carlo codes for neutronics calculation of the IRT-type research reactor

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