Ideas at the Basis of Development of Software for Specific Nuclear Reactor Safety and Design
by Viacheslav Sergeevich Okunev* 
Department of Physics, Bauman Moscow State Technical University, Moscow, 105005, Russia
* Author to whom correspondence should be addressed.
Journal of Engineering Research and Sciences, Volume 1, Issue 5, Page # 01-16, 2022; DOI: 10.55708/js0105001
Keywords: Nuclear reactor, Software, Codes, Optimization methods, Multicriteria problems, Nuclear Fuel
Received: 06 February 2022, Revised: 16 April 2022, Accepted: 21 April 2022, Published Online: 12 May 2022
APA Style
Okunev, V. S. (2022). Ideas at the basis of development of software for specific nuclear reactor safety and design. Journal of Engineering Research and Sciences, 1(5), 1–16. https://doi.org/10.55708/js0105001
Chicago/Turabian Style
Okunev, Viacheslav Sergeevich. “Ideas at the Basis of Development of Software for Specific Nuclear Reactor Safety and Design.” Journal of Engineering Research and Sciences 1, no. 5 (May 2022): 1-16. https://doi.org/10.55708/js0105001.
IEEE Style
V. S. Okunev, “Ideas at the Basis of Development of Software for Specific Nuclear Reactor Safety and Design,” Journal of Engineering Research and Sciences, vol. 1, no. 5, pp. 1–16, May 2022. DOI: 10.55708/js0105001.
The main goal of the work was the development of software and codes for the design of new generation nuclear reactors. The problem is solved by the example of fast reactors with a liquid metal coolant. The problem is solved within the framework of system analysis methods and operations drawing methods. Three groups of methods for solving the problem can be distinguished: optimization methods, methods for calculating stationary states, methods for simulating emergency modes. When designing safe fast reactors, ATWS emergency modes and their combinations are primarily considered. All ATWS modes are grouped into five groups: TOP WS (Transient Overpower without Scram); LOF WS (Loss of Flow without Scram); OVC WS (Overcooling Accident without Scram); LOHS WS (Loss of Heat Sink without Scram) and LOCA WS (Loss of Coolant Accident without Scram). A number of auxiliary discrete multicriteria problems have been solved. To solve them, the method of displaced ideal, lexicographic methods, and maximin strategy of cooperative play were used. Decomposition methods are widely used in research. To solve the multicriteria (two-criterion) problem of continuous optimization, a strategy of sequential decision-making in positional games was used. As a result, a number of codes have been developed that collectively implement the decision-making methodology in the design of nuclear reactors. Among the auxiliary problems, the problems of optimizing the composition of the lead coolant, the problem of optimizing the choice of the fuel composition and structural materials are solved. The choice of parameters that have the greatest impact on the safety of a high-power reactor with a lead coolant is carried out. The proposed algorithms, procedures, methods and codes contribute to solving the problem of designing safe reactors of a new generation – energy sources that will provide human energy on the required scale for the long term.
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