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Bedenko SV, Lutsik IO, Matyushin AA, Polozkov SD, Shmakov VM, Modestov DG, Prikhodko VV, Arzhannikov AV. Fusion-fission hybrid reactor facility: power profiling. NUCLEAR ENERGY AND TECHNOLOGY 2023. [DOI: 10.3897/nucet.9.102781] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 03/19/2023] Open
Abstract
The current state of research in the field of nuclear and thermonuclear power aimed at creating power generation plants makes it possible to predict the further development of modern power industry in the direction hybrid reactor power plants. Such hybrid systems include a tokamak with reactor technologies, worked out in detail in Russia, and systems with an additional source of neutrons.
Power generation plants using tokamaks and accelerators with the required level of proton energy will be of exceptionally large size and power, which will postpone their construction on an industrial scale to the distant future. The ongoing research is aimed at the development of small generation and has the prospect of entering the field of energy use in a shorter period. The hybrid reactor facility under study consists of an axisymmetric assembly of fuel blocks of a high-temperature gas-cooled reactor and a linear plasma source of additional neutrons. The paper demonstrates the results of optimization plasma-physical, thermophysical and gas-dynamic studies, the purpose of which is to level the distortions of the power density field, which are formed in the volume of the multiplicating part of the facility due to the pulsed operation of the plasma source of D-T-neutrons. The studies on increasing the “brightness” of the source and modeling its operating modes were carried out using the DOL and PRIZMA programs. The thermophysical optimization and gas-dynamic calculations were performed using the verified SERPENT and FloEFD software codes. The calculations were made on a high-performance cluster of the Tomsk Polytechnic University.
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Bedenko SV, Lutsik IO, Prikhodko VV, Matyushin AA, Polozkov SD, Shmakov VM, Modestov DG, Vega–Carrillo HR. Neutronic and thermohydraulic blanket analysis for hybrid fusion–fission reactor during operation. NUCLEAR ENGINEERING AND TECHNOLOGY 2023. [DOI: 10.1016/j.net.2023.03.032] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 03/31/2023]
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Wen P, Hu X, Fan C, Tan Y, Qiu W, Zhao T, Li S, Wu C, Du J, Tang J. Irradiation hardening of WK-based PFM exposed to 14 MeV protons. FUSION ENGINEERING AND DESIGN 2023. [DOI: 10.1016/j.fusengdes.2022.113379] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/14/2022]
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Fusion-fission hybrid reactor with a plasma source of deuterium-tritium neutrons in a linear configuration. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104477] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/06/2022]
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Arzhannikov A, Bedenko S, Prikhodko V, Shmakov V, Modestov D, Dolmatov OY, Vega-Carrillo H. A complementary study on the thermophysical and gas-dynamic characteristics of a hybrid fusion–fission reactor facility during operation. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2022.112037] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/06/2022]
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Lai Y, Yang Y. A Design for the High Yield Photoneutron Source Target Station. MATERIALS (BASEL, SWITZERLAND) 2022; 15:7674. [PMID: 36363266 PMCID: PMC9654914 DOI: 10.3390/ma15217674] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Figures] [Subscribe] [Scholar Register] [Received: 09/20/2022] [Revised: 10/27/2022] [Accepted: 10/28/2022] [Indexed: 06/16/2023]
Abstract
Low energy accelerator driven neutron sources are promising candidates to obtain a neutron yield as high as 1014 n/s, which is required for a variety of applications, such as boron neutron capture therapy, neutron imaging, and neutron scattering. The methods to generate neutrons can be divided into two categories: hadron-based and photon-based methods. In order to better understand which kind of source would be the better choice for delivering a brilliant neutron beam robustly, in this paper, the underlying principles of neutron production, as well as the simulation results of neutron yield, target heat dissipation, thermal stress, and reaction byproducts concentration of these two types of neutron sources, will be elaborated on. A preliminary photoneutron target station design based on a 50 MeV/50 kW electron linear accelerator, including the optimized neutron yield, thermal hydraulic analysis, and shielding calculation, is presented as well to demonstrate the method to deliver brilliant thermal neutron beam of 1.03 × 1010 cm-2 s-1 sr-1.
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Affiliation(s)
- Yuxuan Lai
- Department of Engineering Physics, Tsinghua University, Beijing 100084, China
- Key Laboratory of Particle & Radiation Imaging, Tsinghua University, Ministry of Education, Beijing 100084, China
| | - Yigang Yang
- Department of Engineering Physics, Tsinghua University, Beijing 100084, China
- Key Laboratory of Particle & Radiation Imaging, Tsinghua University, Ministry of Education, Beijing 100084, China
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Hirtz J, Letourneau A, Thulliez L, Ibarra A, Krolas W, Maj A. Neutron availability in the Complementary Experiments Hall of the IFMIF-DONES facility. FUSION ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.fusengdes.2022.113133] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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Ortwein R, Kotula J, Wiacek U, Swierblewski J, Bocian D. Hydraulic analysis of the start-up monitoring module (STUMM) for IFMIF-DONES. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112601] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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Dzitko H, Cara P, Carin Y, Chel S, Facco A, Gex D, Hasegawa K, Kasugai A, Kondo K, Massaut V, Molla J, Phillips G, Pisent A, Sakamoto K, Sugimoto M. Status and future developments of the Linear IFMIF Prototype Accelerator (LIPAc). FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112621] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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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. NUCLEAR ENGINEERING AND TECHNOLOGY 2021. [DOI: 10.1016/j.net.2020.11.026] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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11
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LIPAc RF power system: design and main practical implementation issues. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112226] [Citation(s) in RCA: 4] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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Arzhannikov AV, Shmakov VM, Modestov DG, Bedenko SV, Prikhodko VV, Lutsik IO, Shamanin IV. Facility to study neutronic properties of a hybrid thorium reactor with a source of thermonuclear neutrons based on a magnetic trap. NUCLEAR ENGINEERING AND TECHNOLOGY 2020. [DOI: 10.1016/j.net.2020.05.003] [Citation(s) in RCA: 4] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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Shamanin IV, Bedenko SV, Shmakov VM, Modestov DG, Lutsik IO. Power density dynamics in a nuclear reactor with an extended in-core pulse-periodic neutron source based on a magnetic trap. NUCLEAR ENERGY AND TECHNOLOGY 2020. [DOI: 10.3897/nucet.6.57976] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022] Open
Abstract
The article examines the features of the spatial kinetics of an innovative hybrid nuclear power facility with an extended neutron source based on a magnetic trap. The fusion-fission facility under study includes a reactor plant, the core of which consists of an assembly of thorium-plutonium fuel blocks of the HGTRU reactor of a unified design and a long magnetic trap that penetrates the near-axial region of the core. The engineering solution for the neutron plasma generator is based on an operating gas-dynamic trap based on a fusion neutron source (GDT-FNS) developed at the Novosibirsk G.I. Budker Nuclear Physics Institute of the Siberian Branch of the Russian Academy of Sciences. The GDT-FNS high-temperature plasma pinch is formed in pulse-periodic mode in the investigated hybrid facility configuration, and, at a certain pulse rate, one should expect the formation of a fission wave that diverges from the axial part of the system and propagates throughout the fuel block assembly in a time correlation with the fast D-D neutron pulse source. In these conditions, it is essential to study the fission wave propagation process and, accordingly, the power density distribution formation within the facility blanket. The paper presents the results of a study on the steady-state and space-time performances of neutron fluxes and the power density dynamics in the facility under investigation. The steady-state neutronic performance and the space-time fission wave propagation were simulated using the PRIZMA software package developed at FSUE RFNC-VNIITF.
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Pintsuk G, Diegele E, Dudarev SL, Gorley M, Henry J, Reiser J, Rieth M. European materials development: Results and perspective. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2019.02.063] [Citation(s) in RCA: 29] [Impact Index Per Article: 5.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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The strategy toward realization of the helical fusion reactor FFHR-c1. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2019.03.160] [Citation(s) in RCA: 5] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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Tian K, Arbeiter F, Ascott M, Crofts O, McIntyre G, Micciche G, Mitchell G, Qiu Y, Tóth M, Ibarra A. Preliminary analysis on a maintainable test cell concept for IFMIF-DONES. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2019.01.007] [Citation(s) in RCA: 5] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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Al Hamrashdi H, Monk SD, Cheneler D. Passive Gamma-Ray and Neutron Imaging Systems for National Security and Nuclear Non-Proliferation in Controlled and Uncontrolled Detection Areas: Review of Past and Current Status. SENSORS 2019; 19:s19112638. [PMID: 31212632 PMCID: PMC6603774 DOI: 10.3390/s19112638] [Citation(s) in RCA: 20] [Impact Index Per Article: 4.0] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Download PDF] [Figures] [Subscribe] [Scholar Register] [Received: 04/28/2019] [Revised: 05/31/2019] [Accepted: 06/08/2019] [Indexed: 12/04/2022]
Abstract
Global concern for the illicit transportation and trafficking of nuclear materials and other radioactive sources is on the rise, with efficient and rapid security and non-proliferation technologies in more demand than ever. Many factors contribute to this issue, including the increasing number of terrorist cells, gaps in security networks, politically unstable states across the globe and the black-market trading of radioactive sources to unknown parties. The use of passive gamma-ray and neutron detection and imaging technologies in security-sensitive areas and ports has had more impact than most other techniques in detecting and deterring illicit transportation and trafficking of illegal radioactive materials. This work reviews and critically evaluates these techniques as currently utilised within national security and non-proliferation applications and proposes likely avenues of development.
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Affiliation(s)
| | - Stephen D Monk
- Department of Engineering, Lancaster University, Lancaster LA1 4YW, UK.
| | - David Cheneler
- Department of Engineering, Lancaster University, Lancaster LA1 4YW, UK.
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Surrey E. Engineering challenges for accelerated fusion demonstrators. PHILOSOPHICAL TRANSACTIONS. SERIES A, MATHEMATICAL, PHYSICAL, AND ENGINEERING SCIENCES 2019; 377:20170442. [PMID: 30967054 PMCID: PMC6365852 DOI: 10.1098/rsta.2017.0442] [Citation(s) in RCA: 5] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Abstract] [Key Words] [Grants] [Track Full Text] [Subscribe] [Scholar Register] [Accepted: 05/30/2018] [Indexed: 06/09/2023]
Abstract
There are several programmes within the fusion community that are engaged in the design of fusion devices to follow the International Thermonuclear Experimental Reactor (ITER), referred to as 'demonstrators'. These programmes have identified many issues over the past decade, and research now concentrates on optimizing the combination of systems against a set of Key Performance Indicators (KPI) which may vary between programmes. While the return on investment in and experience from ITER is seen as an important factor in this research there are significant differences in the operational conditions and KPI of demonstrators that generate additional problems requiring different solutions. Among these problems are the necessary use of uncommon materials for structural and functional purposes, the impact of the availability KPI on basic machine design, configuration and component lifetime and the integration of the tritium fuel and thermodynamic cycles. These raise issues of component manufacture and standards and of resource availability in the required quantities and quality that are independent of device size and design. Interpreting 'accelerating fusion' in a wider sense, the impact of these issues, analysed in respect of developmental timescales, shows that a strategy of early engagement with the industrial supply chain and the development of computational engineering testing and verification will be essential to prevent prolonged timescales to fusion progress. This article is part of a discussion meeting issue 'Fusion energy using tokamaks: can development be accelerated?'
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Wakai E, Watanabe K, Kondo H, Groeschel F. The design and thermo-structural analysis of target assembly for high intensity neutron source. NUCLEAR MATERIALS AND ENERGY 2018. [DOI: 10.1016/j.nme.2018.07.005] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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Tian K, Ahedo B, Arbeiter F, Barrera G, Ciupiński Ł, Dézsi T, Horne J, Kovács D, Molla J, Mota F, Qiu Y, Schwab F, Siwek M, Tóth M, Varga T, Ibarra A. Overview of the current status of IFMIF-DONES test cell biological shielding design. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.03.043] [Citation(s) in RCA: 11] [Impact Index Per Article: 1.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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Fusion Neutrons: Tritium Breeding and Impact on Wall Materials and Components of Diagnostic Systems. JOURNAL OF FUSION ENERGY 2018. [DOI: 10.1007/s10894-018-0182-1] [Citation(s) in RCA: 24] [Impact Index Per Article: 4.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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22
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Status of the RFQ linac installation and conditioning of the Linear IFMIF Prototype Accelerator. NUCLEAR MATERIALS AND ENERGY 2018. [DOI: 10.1016/j.nme.2018.04.001] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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Ohta M, Kwon S, Sato S, Ochiai K, Suzuki H. Investigation of Mo-99 radioisotope production by d-Li neutron source. NUCLEAR MATERIALS AND ENERGY 2018. [DOI: 10.1016/j.nme.2018.05.017] [Citation(s) in RCA: 10] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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Tian K, Arbeiter F, Gordeev S, Gröschel F, Qiu Y. The test cell configuration under IFMIF-DONES condition. FUSION ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.fusengdes.2017.03.003] [Citation(s) in RCA: 9] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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Knaster J, Favuzza P. Assessment of corrosion phenomena in liquid lithium at T < 873 K. A Li(d,n) neutron source as case study. FUSION ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.fusengdes.2017.03.063] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/27/2022]
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Knaster J, Kanemura T, Kondo K. An assessment of the evaporation and condensation phenomena of lithium during the operation of a Li(d,xn) fusion relevant neutron source. Heliyon 2016; 2:e00199. [PMID: 27981246 PMCID: PMC5144822 DOI: 10.1016/j.heliyon.2016.e00199] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Download PDF] [Figures] [Journal Information] [Subscribe] [Scholar Register] [Received: 05/04/2016] [Revised: 08/24/2016] [Accepted: 11/14/2016] [Indexed: 11/19/2022] Open
Abstract
The flowing lithium target of a Li(d,xn) fusion relevant neutron source must evacuate the deuteron beam power and generate in a stable manner a flux of neutrons with a broad peak at 14 MeV capable to cause similar phenomena as would undergo the structural materials of plasma facing components of a DEMO like reactors. Whereas the physics of the beam-target interaction are understood and the stability of the lithium screen flowing at the nominal conditions of IFMIF (25 mm thick screen with +/-1 mm surface amplitudes flowing at 15 m/s and 523 K) has been demonstrated, a conclusive assessment of the evaporation and condensation of lithium during operation was missing. First attempts to determine evaporation rates started by Hertz in 1882 and have since been subject of continuous efforts driven by its practical importance; however intense surface evaporation is essentially a non-equilibrium process with its inherent theoretical difficulties. Hertz-Knudsen-Langmuir (HKL) equation with Schrage's 'accommodation factor' η = 1.66 provide excellent agreement with experiments for weak evaporation under certain conditions, which are present during a Li(d,xn) facility operation. An assessment of the impact under the known operational conditions for IFMIF (574 K and 10-3Pa on the free surface), with the sticking probability of 1 inherent to a hot lithium gas contained in room temperature steel walls, is carried out. An explanation of the main physical concepts to adequately place needed assumptions is included.
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Affiliation(s)
- J. Knaster
- IFMIF/EVEDA Project Team, F4E, Rokkasho Fusion Institute, Japan
| | - T. Kanemura
- Fusion Energy Research and Development Directorate, QST, Rokkasho Fusion Institute, Japan
| | - K. Kondo
- Fusion Energy Research and Development Directorate, QST, Rokkasho Fusion Institute, Japan
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