Neutron calculations codes applicable to the nuclear power plants safety analysis and safety justification
DOI:
https://doi.org/10.33408/2519-237X.2017.1-3.361Keywords:
Nuclear power plants, safety assessment, safety justification, nuclear reactor, nuclear core, neutron-physical calculations, nuclear codes, safety of nuclear power plantsAbstract
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.
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