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Calculation of the Neutron Parameters for Accelerator-Driven Subcritical Reactors

Science and Technology of Nuclear Installations, 2021-12, Vol.2021, p.1-6 [Peer Reviewed Journal]

Copyright © 2021 Tien Tran Minh and Dung Tran Quoc. ;COPYRIGHT 2021 Hindawi Limited ;Copyright © 2021 Tien Tran Minh and Dung Tran Quoc. This is an open access article distributed under the Creative Commons Attribution License (the “License”), which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited. Notwithstanding the ProQuest Terms and Conditions, you may use this content in accordance with the terms of the License. https://creativecommons.org/licenses/by/4.0 ;ISSN: 1687-6075 ;EISSN: 1687-6083 ;DOI: 10.1155/2021/5284580

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  • Title:
    Calculation of the Neutron Parameters for Accelerator-Driven Subcritical Reactors
  • Author: Tran Minh, Tien ; Tran Quoc, Dung
  • Serikov, Arkady ; Arkady Serikov
  • Subjects: By-products ; Coolants ; Design and construction ; Light water ; Multiplication ; Neutron flux ; Neutrons ; Nuclear energy ; Nuclear reactors ; Parameters ; Proton beams ; Sensors ; Spallation ; Uranium
  • Is Part Of: Science and Technology of Nuclear Installations, 2021-12, Vol.2021, p.1-6
  • Description: In this paper, the accelerator-driven subcritical reactor (ADSR) is simulated based on structure of the TRIGA-Mark II reactor. A proton beam is accelerated and interacts on the lead target. Two cases of using lead are considered here: firstly, solid lead is referred to as spallation neutron target and water as the coolant; secondly, molten lead is considered both as a target and as a coolant. The proton beam in the energy range from 115 MeV to 2000 MeV interacts with the lead to create neutrons. The neutron parameters as neutron yield Yn/p, neutron multiplication factor k, the radial and axial distributions of the neutron flux in the core have been calculated by using MCNPX program. The results show that the neutron yield increases as the energies of the proton beam increases. When using the lead target, the differences between the neutron yield are from 4.2% to 14.2% depending on the energies of the proton beam. The proportion of uranium in the mixtures should be around 24% to produce an effective neutron multiplier factor greater than 0.9. The neutron fluxes are much higher than the same calculations for the TRIGA-Mark II reactor model using tungsten target and light water coolant.
  • Publisher: New York: Hindawi
  • Language: English
  • Identifier: ISSN: 1687-6075
    EISSN: 1687-6083
    DOI: 10.1155/2021/5284580
  • Source: ROAD: Directory of Open Access Scholarly Resources
    ProQuest Central
    DOAJ Directory of Open Access Journals
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