| 1. |
- Chernitskiy, S. V., et al.
(author)
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A fuel cycle for minor actinides burning in a stellarator-mirror fusion-fission hybrid
- 2017
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In: PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. - : KHARKOV INST PHYSICS & TECHNOLOGY. - 1562-6016. ; :1, s. 36-39
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Journal article (peer-reviewed)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.
(author)
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Minor actinides burning in a stellarator-mirror fusion-fission hybrid
- 2015
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In: Problems of Atomic Science and Technology. - 1562-6016. ; :1, s. 20-23
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Journal article (peer-reviewed)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.
(author)
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Neutronic Model Of A Fusion Neutron Source
- 2013
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In: Problems of Atomic Science and Technology. - 1562-6016. ; :1, s. 61-63
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Journal article (peer-reviewed)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.
(author)
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Neutronic Model of a Stellarator-Mirror Fusion-Fission Hybrid
- 2012
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In: PROBL ATOM SCI TECH. - 1562-6016. ; :6, s. 58-60
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Journal article (peer-reviewed)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.
(author)
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Neutronic Model of a Stellarator-Mirror Fusion-Fission Hybrid
- 2013
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In: Fusion science and technology. - 1536-1055 .- 1943-7641. ; 63:1T, s. 322-324
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Journal article (peer-reviewed)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.
(author)
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Static Neutronic Calculation of a Fusion Neutron Source
- 2014
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In: Problems of Atomic Science and Technology. - 1562-6016. ; :6, s. 12-15
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Journal article (peer-reviewed)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.
(author)
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Static neutronic calculation of a subcritical transmutation stellarator-mirror fusion-fission hybrid
- 2014
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In: Annals of Nuclear Energy. - : Elsevier BV. - 0306-4549 .- 1873-2100. ; 72, s. 413-420
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Journal article (peer-reviewed)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.
(author)
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Multiple recycle fuel cycle for spent nuclear fuel components incineration in fusion-fission hybrid
- 2022
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In: Problems of Atomic Science and Technology. - : Problems of Atomic Science and Technology. - 1562-6016. ; :6, s. 40-43
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Journal article (peer-reviewed)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.
(author)
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Research on stellarator-mirror fission-fusion hybrid
- 2014
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In: Plasma Physics and Controlled Fusion. - : IOP Publishing. - 0741-3335 .- 1361-6587. ; 56:9, s. 094008-
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Journal article (peer-reviewed)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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