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Advances in Materials Science and Engineering
Volume 2015, Article ID 392721, 8 pages
http://dx.doi.org/10.1155/2015/392721
Research Article

Gas-Cooled Thorium Reactor with Fuel Block of the Unified Design

National Research Tomsk Polytechnic University, 30 Lenin Avenue, Tomsk 634050, Russia

Received 5 June 2015; Revised 11 August 2015; Accepted 16 August 2015

Academic Editor: Amritendu Roy

Copyright © 2015 Igor Shamanin et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

Abstract

Scientific researches of new technological platform realization carried out in Russia are based on ideas of nuclear fuel breeding in closed fuel cycle and physical principles of fast neutron reactors. Innovative projects of low-power reactor systems correspond to the new technological platform. High-temperature gas-cooled thorium reactors with good transportability properties, small installation time, and operation without overloading for a long time are considered perspective. Such small modular reactor systems at good commercial, competitive level are capable of creating the basis of the regional power industry of the Russian Federation. The analysis of information about application of thorium as fuel in reactor systems and its perspective use is presented in the work. The results of the first stage of neutron-physical researches of a 3D model of the high-temperature gas-cooled thorium reactor based on the fuel block of the unified design are given. The calculation 3D model for the program code of MCU-5 series was developed. According to the comparison results of neutron-physical characteristics, several optimum reactor core compositions were chosen. The results of calculations of the reactivity margins, neutron flux distribution, and power density in the reactor core for the chosen core compositions are presented in the work.