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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
- Source :
- Nuclear Engineering and Technology, Vol 53, Iss 6, Pp 1736-1746 (2021)
- Publication Year :
- 2021
- Publisher :
- Elsevier BV, 2021.
-
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.
- Subjects :
- Work (thermodynamics)
Materials science
020209 energy
Nuclear engineering
chemistry.chemical_element
02 engineering and technology
Plasma pulse-periodic generator
Blanket
030218 nuclear medicine & medical imaging
03 medical and health sciences
0302 clinical medicine
0202 electrical engineering, electronic engineering, information engineering
Hybrid reactor
Neutron
Thorium-containing fuel
Nuclear Experiment
Fusion
Hybrid fusion–fission reactor
D-T neutrons
Wave» fissions
TK9001-9401
Thorium
Thorium fuel cycle
Core (optical fiber)
Nuclear Energy and Engineering
chemistry
Nuclear engineering. Atomic power
Physics::Accelerator Physics
Subjects
Details
- ISSN :
- 17385733
- Volume :
- 53
- Database :
- OpenAIRE
- Journal :
- Nuclear Engineering and Technology
- Accession number :
- edsair.doi.dedup.....87a3b90c06f6779fc80c9c5a39dc5a2d