Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Maintaining the close-to-critical state of thorium fuel core of hybrid reactor operated under control by D-T fusion neutron flux

  • Bedenko, Sergey V. (National Research Tomsk Polytechnic University) ;
  • Arzhannikov, Andrey V. (Budker Institute of Nuclear Physics of Siberian Branch Russian Academy of Sciences) ;
  • Lutsik, Igor O. (National Research Tomsk Polytechnic University) ;
  • Prikhodko, Vadim V. (Budker Institute of Nuclear Physics of Siberian Branch Russian Academy of Sciences) ;
  • Shmakov, Vladimir M. (Federal State Unitary Enterprise (Russian Federal Nuclear Center - Zababakhin All-Russia Research Institute of Technical Physics)) ;
  • Modestov, Dmitry G. (Federal State Unitary Enterprise (Russian Federal Nuclear Center - Zababakhin All-Russia Research Institute of Technical Physics)) ;
  • Karengin, Alexander G. (National Research Tomsk Polytechnic University) ;
  • Shamanin, Igor V. (National Research Tomsk Polytechnic University)
  • Received : 2020.10.05
  • Accepted : 2020.11.27
  • Published : 2021.06.25
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Abstract

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

Keywords

Acknowledgement

This research was supported by RFBR and RNF, Project no.19-29-02005 and no.18-19-00136, and by Tomsk Polytechnic University, CEP Grant no.DRIaP_75/2019.

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