| 1. |
- Chernitskiy, S. V., et al.
(författare)
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A fuel cycle for minor actinides burning in a stellarator-mirror fusion-fission hybrid
- 2017
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Ingår i: PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. - : KHARKOV INST PHYSICS & TECHNOLOGY. - 1562-6016. ; :1, s. 36-39
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Tidskriftsartikel (refereegranskat)abstract
- The MCNPX Monte-Carlo code has been used to model a concept of a fusion-fission stellarator-mirror hybrid aimed for transmutation transuranic content from the spent nuclear fuel. A fuel cycle for the subcritical fusion-fission hybrid is investigated and discussed.
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| 2. |
- Chernitskiy, S. V., et al.
(författare)
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Minor actinides burning in a stellarator-mirror fusion-fission hybrid
- 2015
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Ingår i: Problems of Atomic Science and Technology. - 1562-6016. ; :1, s. 20-23
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Tidskriftsartikel (refereegranskat)abstract
- The MCNPX Monte-Carlo code has been used to model a compact concept of a fusion-fission reactor based on a combined stellarator-mirror trap for transmutation transuranic elements from the spent nuclear fuel. Calculation results for fission rates for transuranic elements are presented.
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| 3. |
- Chernitskiy, S. V., et al.
(författare)
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Neutronic Model Of A Fusion Neutron Source
- 2013
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Ingår i: Problems of Atomic Science and Technology. - 1562-6016. ; :1, s. 61-63
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Tidskriftsartikel (refereegranskat)abstract
- The MCNPX numerical code has been used to model a fusion neutron source based on a combined stellarator-mirror trap. Calculation results for the neutron spectrum near the inner wall and radial leakage of neutrons through the mantle surface of the fusion neutron source are presented.
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| 4. |
- Chernitskiy, S. V., et al.
(författare)
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Neutronic Model of a Stellarator-Mirror Fusion-Fission Hybrid
- 2012
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Ingår i: PROBL ATOM SCI TECH. - 1562-6016. ; :6, s. 58-60
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Tidskriftsartikel (refereegranskat)abstract
- The MCNPX numerical code has been used to model a compact concept for a fusion-fission reactor based on a combined stellarator-mirror trap. Calculation results for the radial leakage of neutrons through the mantle surface of the fission reactor are presented.
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| 5. |
- Chernitskiy, S. V., et al.
(författare)
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Neutronic Model of a Stellarator-Mirror Fusion-Fission Hybrid
- 2013
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Ingår i: Fusion science and technology. - 1536-1055 .- 1943-7641. ; 63:1T, s. 322-324
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Tidskriftsartikel (refereegranskat)abstract
- The MCNPX numerical code has been used to model the neutron transport in a mirror based fusion-fission reactor. The purpose is to find a principal design of the fission mantle which fits to the neutron source and to calculate the leakage of neutrons through the mantle surface of the fission reactor. The fission reactor part has a cylindrical shape with an outer radius 1.66 m and a 4 m length. The fuel has the isotopic composition of the spent nuclear fuel from PWR after uranium-238 removal. Inside the fission reactor core is a vacuum chamber with a radius 0.5 m containing a 4 m long hot plasma producing fusion neutrons. To sustain the hot ion plasma which is responsible for the fusion neutron production, neutral beam injection is considered. Calculation results for the radial leakage of neutrons through the mantle surface of the fission reactor are presented. These calculations predict that the power released with neutrons from the reactor to outer space would be small and will not exceed the value of 6 kW while the reactor thermal power is 1 GWth.
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| 6. |
- Chernitskiy, S. V., et al.
(författare)
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Static Neutronic Calculation of a Fusion Neutron Source
- 2014
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Ingår i: Problems of Atomic Science and Technology. - 1562-6016. ; :6, s. 12-15
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Tidskriftsartikel (refereegranskat)abstract
- The MCNPX numerical code has been used to model a fusion neutron source based on a combined stellarator-mirror trap. Calculation results for the neutron flux and spectrum inside the first wall are presented. Heat load and irradiation damage on the first wall are calculated.
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| 7. |
- Chernitskiy, S. V., et al.
(författare)
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Static neutronic calculation of a subcritical transmutation stellarator-mirror fusion-fission hybrid
- 2014
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Ingår i: Annals of Nuclear Energy. - : Elsevier BV. - 0306-4549 .- 1873-2100. ; 72, s. 413-420
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Tidskriftsartikel (refereegranskat)abstract
- The MCNPX Monte-Carlo code has been used to model the neutron transport in a sub-critical fast fission reactor driven by a fusion neutron source. A stellarator-mirror device is considered as the fusion neutron source. The principal composition for a fission blanket of a mirror fusion-fission hybrid is devised from the calculations. Heat load on the first wall, the distribution of the neutron fields in the reactor, the neutron spectrum and the distribution of energy release in the blanket are calculated. The possibility of tritium breeding inside the installation in quantities that meet the needs of the fusion neutron source is analyzed. The portion of the plasma column generates fusion neutrons that mainly do not reach the fission reactor core is proposed to be surrounded by a vessel filled with borated water to absorb the flying out neutrons. The flux of the neutrons escaping from the device to surrounding space is also calculated.
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| 8. |
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| 9. |
- Moiseenko, Vladimir E., et al.
(författare)
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Multiple recycle fuel cycle for spent nuclear fuel components incineration in fusion-fission hybrid
- 2022
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Ingår i: Problems of Atomic Science and Technology. - : Problems of Atomic Science and Technology. - 1562-6016. ; :6, s. 40-43
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Tidskriftsartikel (refereegranskat)abstract
- A multiple recycle fuel cycle (MRFC) is analyzed using a simple numerical model. A straightforward approach to MRFC has some unfavorable features like strong variation of the neutron multiplication factor and accumulation of americium isotopes which would likely hamper its practical usage. A solution proposed here is addition of 238U both to initial fuel and the recycled fuel.
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| 10. |
- Moiseenko, V. E., et al.
(författare)
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Research on stellarator-mirror fission-fusion hybrid
- 2014
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Ingår i: Plasma Physics and Controlled Fusion. - : IOP Publishing. - 0741-3335 .- 1361-6587. ; 56:9, s. 094008-
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Tidskriftsartikel (refereegranskat)abstract
- The development of a stellarator-mirror fission-fusion hybrid concept is reviewed. The hybrid comprises of a fusion neutron source and a powerful sub-critical fast fission reactor core. The aim is the transmutation of spent nuclear fuel and safe fission energy production. In its fusion part, neutrons are generated in deuterium-tritium (D-T) plasma, confined magnetically in a stellarator-type system with an embedded magnetic mirror. Based on kinetic calculations, the energy balance for such a system is analyzed. Neutron calculations have been performed with the MCNPX code, and the principal design of the reactor part is developed. Neutron outflux at different outer parts of the reactor is calculated. Numerical simulations have been performed on the structure of a magnetic field in a model of the stellarator-mirror device, and that is achieved by switching off one or two coils of toroidal field in the Uragan-2M torsatron. The calculations predict the existence of closed magnetic surfaces under certain conditions. The confinement of fast particles in such a magnetic trap is analyzed.
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| 11. |
- Moiseenko, V. E., et al.
(författare)
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Stellarator-mirror fusion-fission hybrid - a fast route to clean and safe nuclear energy
- 2023
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Ingår i: Journal of Plasma Physics. - : Cambridges Institutes Press. - 0022-3778 .- 1469-7807. ; 89:4
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Tidskriftsartikel (refereegranskat)abstract
- The multiple-recycle fuel cycle for uranium-238 considered here, if practically realized, can bring revolutionary changes in nuclear energy. A full use of uranium-238 implies a practically infinite resource for power generation. Besides the energy, the fuel cycle net output is only fission products, which are co-products rather than waste. For the same amount of energy produced, the amount of fission products is two orders of magnitude less compared with the amount of spent nuclear fuel generated in currently exploited nuclear energy production scenarios. Using the simplest isotope balance model, key features of the multiple-recycle fuel cycle for uranium-238 are investigated. The repetition of this cycle results in smooth transformation of the initial fuel to 'stationary' fuel without strong variations in the fractional isotope content. Deficit of delayed neutrons is a threat of the fuel cycle considered as well as other fuel cycles that use plutonium. It has a dramatic impact on reactor controllability and safety. A solution to this threat could be a subcritical nuclear reactor with an external neutron source. In this paper, use of a stellarator-mirror (SM) fusion-fission hybrid for the multiple-recycle fuel cycle for uranium-238 is analysed. A summary of the experimental and theoretical studies on the SM hybrid is given. Preliminary results for principal design of a SM hybrid nuclear reactor for the multiple-recycle fuel cycle for uranium-238 are presented.
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| 12. |
- Moiseyenko, Volodymyr, et al.
(författare)
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Americium and Curium Burnup in a Fusion Reactor
- 2021
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Ingår i: Problems of Atomic Science and Technology, Ser. Thermonuclear Fusion. - : NRC Kurchatov Institute. - 0202-3822. ; 44:2, s. 133-138
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Tidskriftsartikel (refereegranskat)abstract
- A large amount of spent nuclear fuel (SNF) from nuclear power plants has been accumulated globally to date, and there is still no established strategy for handling it. While SNF can be partitioned, the predominant isotope Uranium-238 can be used to produce secondary fuel in fast nuclear reactors, and plutonium be burned in thermal nuclear reactors as a part of MOX fuel. Fission products can be disposed in geological repositories, as they decay in 200—300 years — much sooner than SNF. A major challenge is to handle minor actinides (MAs), particularly americium and curium, which are long-lived elements and are currently not recycled. They have different nuclear properties and cannot be treated like plutonium. It is possible to have americium and curium effectively burned up (fissioned) through irradiation with fusion neutrons. This paper explores the idea of employing fusion power plants for recycling those elements. An appropriate model was generated, which used americium and curium quantities small enough to avoid any strong impact on the reactor systems and operation. At the same time, the model allowed for high MA burnup rates. Nuclear facility used in the model was a torus-shaped thermonuclear reactor with plasma major and minor radii of 1000 and 300 cm, respectively. Such facility could take up additional 10 t of fuel (americium plus curium) with no significant impact on its physical characteristics. The americium and curium burnup rates, calculated with the MNCPX code, were within acceptable limits. Fission neutrons were found to contribute to the production of tritium, which may be important from the standpoint of the reactor’s self-sufficiency in tritium supply. Calculations proved that the reactivity of the reactor as a fission burner was low, enabling a safe operation. In addition to the MA incineration and tritium breeding capacities, fission reactions provided for a moderate (tens of percent) power gain.
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| 13. |
- Moiseyenko, Volodymyr, et al.
(författare)
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Developments for stellarator-mirror fusion-fission hybrid concept
- 2021
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Ingår i: Problems of Atomic Science and Technology, Ser. Thermonuclear Fusion. - : NRC Kurchatov Institute. - 0202-3822. ; 44:2, s. 111-117
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Tidskriftsartikel (refereegranskat)abstract
- Conceptual development activities on a stellarator-mirror-based fission-fusion hybrid system (SM hybrid) are reviewed. Intended fortransmutation of spent nuclear fuel and safe fission energy production, SM hybrid consists of a fusion neutron source and a powerful subcritical fast fission reactor core. Its fusion component is a stellarator with an embedded magnetic mirror. The stellarator allows for theconfinement of a moderately hot (1—2 keV) deuterium plasma. In the magnetic mirror, the hot sloshing tritium ions are trapped andfusion neutrons are generated. The magnetic mirror is surrounded by a fission mantle, where transmutation of minor actinides and energygeneration take place. One candidate magnetic confinement device for the SM hybrid is the advanced DRACON magnetic trap system,which, unlike the «classical» DRACON version, has one short, rather than two longer mirrors with a relatively short size of 3—6 m. Acomparative numerical analysis of collisionless losses occurring in the magnetic trap part of the single-mirror DRACON leads to a conclusion about the possibility for high-energy tritium ions to be fairly well confined in the magnetic trap area. The Uragan-2M (U-2M)stellarator is used to test the SM hybrid concept with experiment. To fit a magnetic trap into U-2M system, one of the toroidal coils hadto be switched off. A radial escape of charged particles may spontaneously give rise to a weak radial electric field, which may result inclosing the particles’ drift trajectories and thereby substantially improve their confinement. Background plasma confinement withoutdestructive instabilities is demonstrated in the stellarator-mirror regime of U-2M) operation. The sloshing ions driven by radio-frequencyheating are detected in the mirror part of the device with NPA diagnostics. A novel fission mantle design for the SM hybrid is proposed.
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| 14. |
- Ågren, Olov, et al.
(författare)
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Steady-state fusion fission reactor concepts based on stellarator-mirror and mirror machines
- 2015
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Ingår i: Problems of Atomic Science and Technology. - 1562-6016. ; :1, s. 3-7
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Tidskriftsartikel (refereegranskat)abstract
- Neutron sources and hybrid reactors offer a possibility for application of fusion in a not too distant future. Steady-state operation on a time scale of a year without interruption is essential for such applications. In response to this need, our studies are focused on concepts which are not limited by pulsed operation. Special attention is put on mirror machines and a stellarator-mirror concept with localized neutron production. Reactor safety, magnetic coils, power amplification by fission, plasma heating, a radial constant of motion which provides a bounded radial motion in the collision free approximation are some of the issues addressed.
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