Modeling of operating history of the research nuclear reactor

A. Naymushin, Yu Chertkov, M. Shchurovskaya, M. Anikin, I. Lebedev

Division for Nuclear-Fuel Cycle

Research output: Contribution to journal › Conference article › peer-review

Abstract

The results of simulation of the IRT-T reactor operation history from 2012 to 2014 are presented. Calculations are performed using continuous energy Monte Carlo code MCU-PTR. Comparison is made between calculation and experimental data for the critical reactor.

Original language	English
Article number	012032
Journal	IOP Conference Series: Materials Science and Engineering
Volume	135
Issue number	1
DOIs	https://doi.org/10.1088/1757-899X/135/1/012032
Publication status	Published - 2 Aug 2016
Event	8th International Scientific Conference on Issues of Physics and Technology in Science, Industry and Medicine - Tomsk, Russian Federation Duration: 1 Jun 2016 → 3 Jun 2016

ASJC Scopus subject areas

Materials Science(all)
Engineering(all)

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title = "Modeling of operating history of the research nuclear reactor",

abstract = "The results of simulation of the IRT-T reactor operation history from 2012 to 2014 are presented. Calculations are performed using continuous energy Monte Carlo code MCU-PTR. Comparison is made between calculation and experimental data for the critical reactor.",

author = "A. Naymushin and Yu Chertkov and M. Shchurovskaya and M. Anikin and I. Lebedev",

year = "2016",

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AU - Naymushin, A.

AU - Chertkov, Yu

AU - Shchurovskaya, M.

AU - Anikin, M.

AU - Lebedev, I.

PY - 2016/8/2

Y1 - 2016/8/2

N2 - The results of simulation of the IRT-T reactor operation history from 2012 to 2014 are presented. Calculations are performed using continuous energy Monte Carlo code MCU-PTR. Comparison is made between calculation and experimental data for the critical reactor.

AB - The results of simulation of the IRT-T reactor operation history from 2012 to 2014 are presented. Calculations are performed using continuous energy Monte Carlo code MCU-PTR. Comparison is made between calculation and experimental data for the critical reactor.

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DO - 10.1088/1757-899X/135/1/012032

M3 - Conference article

AN - SCOPUS:84995646140

VL - 135

JO - IOP Conference Series: Materials Science and Engineering

JF - IOP Conference Series: Materials Science and Engineering

SN - 1757-8981

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T2 - 8th International Scientific Conference on Issues of Physics and Technology in Science, Industry and Medicine

Y2 - 1 June 2016 through 3 June 2016

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Modeling of operating history of the research nuclear reactor

Abstract

ASJC Scopus subject areas

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