| 1. |
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| 2. |
- 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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| 3. |
- 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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| 4. |
- 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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| 5. |
- 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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| 6. |
- 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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| 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. |
- Källne, Jan, et al.
(författare)
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Neutron Diagnostics For Mirror Hybrids
- 2012
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Ingår i: Fusion for Neutrons and Subcritical Nuclear Fission. - : AIP. - 9780735410381 ; , s. 281-288
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Konferensbidrag (refereegranskat)abstract
- Fusion-fission (FuFi) hybrids will need instrumentation to diagnose the deuterium-tritium plasma, whose 14-MeV neutron emission is the driver of the sub-critical fission core. While the fission neutron yield rate (Y-fi and hence power P-fi) can be monitored with standard instrumentation, fusion plasmas in hybrids require special diagnostics where the determination of Y-th (proportional to P-fu) is a challenge. Information on Y-fu is essential for assessing the fusion plasma performance which together with Y-fi allows for the validation of the neutron multiplication factor (k) of the subcritical fission core. Diagnostics for hybrid plasmas are heuristically discussed with special reference to straight field line mirror (SFLM). Relevant DT plasma experience from JET and plans for ITER in the main line of fusion research were used as input. It is shown that essential SFLM plasma information can potentially be obtained with proposed instrumentation, but the state of the hybrid plasma must be predictably robust as derived from fully diagnosed dedicated experiments without interface restrictions of the hybrid application.
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| 9. |
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| 10. |
- Moiseenko, Vladimir E., et al.
(författare)
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Stellarator-Mirror Based Fusion Driven Fission Reactor
- 2010
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Ingår i: Journal of fusion energy. - : Springer Science and Business Media LLC. - 0164-0313 .- 1572-9591. ; 29:1, s. 65-69
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Tidskriftsartikel (refereegranskat)abstract
- The version of fusion driven system (FDS), a sub-critical fast fission assembly with a fusion plasma neutron source, theoretically investigated here is based on a stellarator with a small mirror part. In the magnetic well of the mirror part, fusion reactions occur from collision of an RF heated hot ion component (tritium), with high perpendicular energy with cold background plasma ions. The hot ions are assumed to be trapped in the magnetic mirror part. The stellarator part which connects to the mirror part provides confinement for the bulk (deuterium) plasma. Calculations based on a power balance analysis indicate the possibility to achieve a net electric power output with a compact FDS device. For representative thermal power output of a power plant (P th ≈ P fis = 0.5–2 GW) the computed electric Q-factor is in the range Q el = 8–14, which indicates high efficiency of the FDS scheme.
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