MAINTAINING THE CLOSE-TO-CRITICAL STATE OF THORIUM FUEL CORE OF HYBRID REACTOR OPERATED UNDER CONTROL BY D-T FUSION NEUTRON FLUX

Sergey V. Bedenko; Andrey V. Arzhannikov; Igor O. Lutsik; Vadim V. Prikhodko; Vladimir M. Shmakov; Dmitry G. Modestov; Alexander G. Karengin; Igor V. Shamanin

doi:https://doi.org/10.1016/j.net.2020.11.026

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자료유형: 학술저널

저자정보: Sergey V. Bedenko (National Research Tomsk Polytechnic University) Andrey V. Arzhannikov (Budker Institute of Nuclear Physics of Siberian Branch Russian Academy of Sciences) Igor O. Lutsik (National Research Tomsk Polytechnic University) Vadim V. Prikhodko (Budker Institute of Nuclear Physics of Siberian Branch Russian Academy of Sciences) Vladimir M. Shmakov (Federal State Unitary Enterprise ≪Russian Federal Nuclear Center - Zababakhin All-Russia Research I) Dmitry G. Modestov (Federal State Unitary Enterprise ≪Russian Federal Nuclear Center - Zababakhin All-Russia Research I) Alexander G. Karengin (National Research Tomsk Polytechnic University) Igor V. Shamanin (National Research Tomsk Polytechnic University)

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제53권 제6호

발행연도: 2021.6

수록면: 1,736 - 1,746 (11page)

DOI: https://doi.org/10.1016/j.net.2020.11.026

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The results of full-scale numerical experiments of a hybrid thorium-containing fuel cell facility operatingin a close-to-critical state due to a controlled source of fusion neutrons are discussed in this work. Thefacility under study was a complex consisting of two blocks. The first block was based on the concept of ahigh-temperature gas-cooled thorium reactor core. The second block was an axially symmetricalextended plasma generator of additional neutrons that was placed in the near-axial zone of the facilityblanket. The calculated models of the blanket and the plasma generator of D-T neutrons created withinthe work allowed for research of the neutronic parameters of the facility in stationary and pulse-periodicoperation modes. This research will make it possible to construct a safe facility and investigate theproperties of thorium fuel, which can be continuously used in the epithermal spectrum of the consideredhybrid fusionefission reactor.

#Wave fissions #Plasma pulse-periodic generator #D-T neutrons #Hybrid fusionefission reactor #Thorium-containing fuel

참고문헌 (28)

참고문헌 신청

G. Locatelli / 2014 / Small modular reactors : a comprehensive overview of their economics and strategic aspects / Prog. Nucl. Energy 73:75~85

M. K. Rowinski / 2015 / Small and Medium sized Reactors : a review of technology / Renew. Sustain. Energy Rev 44:643~656

H. E. Garcia / 2013 / Dynamic analysis of hybrid energy systems under flexible operation and variable renewable generationePart I : dynamic performance analysis / Energy 52:1~16

G. Black / 2015 / Carbon free energy development and the role of small modular reactors : a review and decision framework for deployment in developing countries / Renew. Sustain. Energy Rev 43:83~94

I. V. Shamanin / 2018 / Neutronic properties of high-temperature gas-cooled reactors with thorium fuel / Ann. Nucl. Energy 113:286~293

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