Neutronic properties of high-temperature gas-cooled reactors with thorium fuel

I. V. Shamanin, V. M. Grachev, Yu B. Chertkov, S. V. Bedenko, O. Mendoza, V. V. Knyshev

Research output: Contribution to journal › Article

Abstract

High-temperature gas-cooled low-power thorium reactor units (RU) serve as ideal sources of heat energy for supply to remote areas, large naval bases and military garrisons. This study is focused on neutronic characteristics of a 60-MWth low-power thorium reactor core with fuel blocks and pellets of different configurations. The optimal configuration was selected from these combinations and enabled the reactor to operate for a minimum of 3000 days at a capacity of 60 MWth. Additionally, this study investigated the use of burnable absorber ZrB₂ sprayed onto the lateral surface of the fuel pellets in the reactor to reduce the initial excess reactivity.

Original language	English
Pages (from-to)	286-293
Number of pages	8
Journal	Annals of Nuclear Energy
Volume	113
DOIs	https://doi.org/10.1016/j.anucene.2017.11.045
Publication status	Published - 1 Mar 2018

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Keywords

Long-life core
Low-power thorium reactor
Thorium

ASJC Scopus subject areas

Nuclear Energy and Engineering

Cite this

Shamanin, I. V., Grachev, V. M., Chertkov, Y. B., Bedenko, S. V., Mendoza, O., & Knyshev, V. V. (2018). Neutronic properties of high-temperature gas-cooled reactors with thorium fuel. Annals of Nuclear Energy, 113, 286-293. https://doi.org/10.1016/j.anucene.2017.11.045

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AU - Mendoza, O.

AU - Knyshev, V. V.

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Access to Document

10.1016/j.anucene.2017.11.045