Neutron calculations codes applicable to the nuclear power plants safety analysis and safety justification

Authors

  • Sergey S. Tret'yakevich Department for Nuclear and Radiation Safety of the Ministry for Emergency Situations of the Republic of Belarus; ul. Bersona, 16, Minsk, 220030, Belarus
  • Filipp A. Speranskiy Department for Nuclear and Radiation Safety of the Ministry for Emergency Situations of the Republic of Belarus; ul. Bersona, 16, Minsk, 220030, Belarus

DOI:

https://doi.org/10.33408/2519-237X.2017.1-3.361

Keywords:

Nuclear power plants, safety assessment, safety justification, nuclear reactor, nuclear core, neutron-physical calculations, nuclear codes, safety of nuclear power plants

Abstract

Purpose. The aim of authors was to consider the neutron-physical software of various countries used to analyse and justify the safety of the nuclear power plant in terms determination of the parameters of the nuclear power plant unit core in various operating modes, calculating the fuel campaign, burnup and etc.

Methods. In-depth analysis was applied for definition of the characteristics of the calculation codes spectrum.

Findings. The range of most beneficially applicable neutron calculations codes were sorted during whole spectrum overview.

Application field of research. Safety assessment and safety justification of nuclear power plants design and structure are in the area of high importance for Belarusian society. As far as officials has a responsibility for actual safety state ascertaining it is important to stay in line with best practices approved internationally. Conclusion. Thus the suggestions concerning neutron calculations codes application in Belarusian expert (technical support) and operating organisations were prepared.

Author Biographies

Sergey S. Tret'yakevich, Department for Nuclear and Radiation Safety of the Ministry for Emergency Situations of the Republic of Belarus; ul. Bersona, 16, Minsk, 220030, Belarus

Deputy Head of Department

Filipp A. Speranskiy, Department for Nuclear and Radiation Safety of the Ministry for Emergency Situations of the Republic of Belarus; ul. Bersona, 16, Minsk, 220030, Belarus

Chief Specialist

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Published

2017-08-14

How to Cite

Tret’yakevich С. and Speranskiy Ф. (2017) “Neutron calculations codes applicable to the nuclear power plants safety analysis and safety justification”, Journal of Civil Protection, 1(3), pp. 361–372. doi: 10.33408/2519-237X.2017.1-3.361.