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Numerical study of plasmas start-up by electron cyclotron waves in NCST spherical tokamak and CN-H1 stellarator

Plasma Science and Technology 2024年第7期26卷 12-22页

作者：刘亿卓行郑平卫龚学余尹岚陈小昌钟翊君杨文军 School of Nuclear Science and Technology University of South ChinaHengyang 421001People’s Republic of China School of Resource Environmentand Safety EngineeringUniversity of South ChinaHengyang 421001People’s Republic of China School of Electrical Engineering University of South ChinaHengyang 421001People’s Republic of China School of Physics and Materials Nanchang UniversityNanchang 330031People’s Republic of China

According to the physics of tokamak start-up,this study constructs a zero-dimensional(0D)model applicable to electron cyclotron(EC)wave assisted start-up in NCST spherical torus(spherical tokamak)and CN-H1 *** the constructed 0D model,the results obtained in this study under the same conditions are compared and validated against reference results for pure hydrogen plasma start-up in *** results are in good agreement,especially regarding electron temperature,ion temperature and plasma *** the presence of finite Ohmic electric field in the spherical tokamak,a study on the EC wave assisted start-up of the NCST plasma at frequency of 28 GHz is *** impact of the vertical magnetic field B_(v)on EC wave assisted start-up,the relationship between EC wave injection power P_(inj),Ohmic electric field E,and initial hydrogen atom density n_(H0)are explored *** is found that under conditions of Ohmic electric field lower than ITER(~0.3 V m^(-1)),EC wave can expand the operational space to achieve better plasma *** the process of28 GHz EC wave start-up in the CN-H1 stellarator plasma,the plasma current in the zerodimensional model is replaced with the current in the poloidal coil of the *** startup can be successfully achieved at injection powers in the hundreds of kilowatts range,resulting in electron densities on the order of 10^(17)-10^(18)m^(-3).

关键词： spherical torus stellarator electron cyclotron wave start-up 0D model

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The Parameters of the stellarator as a Neutron Source for a Subcritical Reactor

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Journal of Physical Science and Application 2014年第2期4卷 90-99页

作者： Vasiliy Rudakov Institute of Plasma Physics National Science Center "Kharkov Institute of Physics and Technology" Kharkov 61108 Ukraine

The possibility of developing a stellarator-based neutron source designed for the nuclear reaction initiation in the blanket of hybrid reactor is studied. An analog of the Large Helical Device （LHD） stellarator design, with linear dimensions increased by a factor of 1.5 is taken for the magnetic system. Plasma parameters and the deuterium-tritium （DT） mixture fusion power are calculated using the space-time numerical code under the assumption of the neoclassical transport in the ambipolarity regime. Using the 10 MW plasma heating sources, it is possible to obtain the DT fusion power of one-to-two tens MW.

关键词： stellarator subcritical reactor ambipolar electric field neoclassical transport neutron source fusion power

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Investigation of turbulence rotation in the SOL and plasma edge of W7-X for different magnetic configurations

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Plasma Science and Technology 2020年第6期22卷 21-31页

作者： A KRÄMER-FLECKEN X HAN M OTTE G ANDA S A BOZHENKOV D DUNAI G FUCHERT J GEIGER O GRULKE E PASCH E R SCOTT E TRIER M VÉCSEI T WINDISCH S ZOLETNIK W7-X Team Institute for Energy-and Climate Research/Plasma Physics Forschungszentrum Jülich GmbH52425 JülichGermany Institute of Plasma Physics Chinese Academy of SciencesHefei 230031People's Republic of China Max Planck Institut für Plasmaphysik 17491 GreifswaldGermany Wigner Research Centre for Physics 1525 BudapestHungary Max Planck Institut für Plasmaphysik 85748 GarchingGermany 不详

The W7-X stellarator is optimized with respect to neoclassical *** turbulent transport plays an important *** is equipped with an inertial cooled graphite divertor which intersects the island chain at the plasma edge depending on the magnetic *** control coils and the plasma current modify the iota profile at the plasma edge and shift the position of the island *** monitor the effects on the poloidal propagation velocity in the scrape-off layer(SOL)and the plasma edge,an O-mode Poloidal Correlation Reflectometer(PCR)is used which simultaneously monitors the propagation of low-k *** in the density range of 0.6?×?1019 m-3 to2?×?1019 m-3 it covers a large part of the SOL and the plasma edge and allows for the experimental determination in the last closed flux surface(LCFS)and the associated shear layer in low to middensity *** this paper it is shown that the propagation in the shear layer and its vicinity is determined best,when based on an elliptical *** magnetic configurations with magnetic edge topology of five independent islands forι?=?1 and six linked islands forι?=?0.81 are *** the effects of the plasma current and additional control coils on the edge magnetic topology are *** coherence spectra of antenna pairs for different poloidal separations is *** a decomposition method for the measured coherence spectra the characterization of turbulence spectra is possible with respect to *** band turbulence and quasi coherent modes.A strong reduction of the broad band turbulence is observed in the vicinity of the LCFS which is evidence for the suppression of low-k turbulence at the shear layer.

关键词： stellarator correlation reflectometer turbulence rotation scrape-off layer island divertor

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Progressive Thermalization Fusion Reactor Able to Produce Nuclear Fusions at Higher Mechanical Gain

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Energy and Power Engineering 2022年第1期14卷 35-100页

作者： Patrick Lindecker Maisons-Alfort France

In the standard fusion reactors, mainly tokamaks, the mechanical gain obtained is below 1. On the other hand, there are colliding beam fusion reactors, for which, the not neutral plasma and the space charge limit the number of fusions to a very small number. Consequently, the mechanical gain is extremely low. The proposed reactor is also a colliding beam fusion reactor, configured in stellarator, using directed beams. D+/T+ ions are injected in opposition, with electrons, at high speeds, so as to form a neutral beam. All these particles turn in a magnetic loop in form of figure of “0” (“racetrack”). The plasma is initially non-thermal but, as expected, rapidly becomes thermal, so all states between non-thermal and thermal exist in this reactor. The main advantage of this reactor is that this plasma after having been brought up near to the optimum conditions for fusion (around 68 keV), is then maintained in this state, thanks to low energy non-thermal ions (≤15 keV). So the energetic cost is low and the mechanical gain (Q) is high (>>1). The goal of this article is to study a different type of fusion reactor, its advantages (no net plasma current inside this reactor, so no disruptive instabilities and consequently a continuous working, a relatively simple way to control the reactor thanks to the particles injectors), and its drawbacks, using a simulator tool. The finding results are valuable for possible future fusion reactors able to generate massive energy in a cleaner and safer way than fission reactors.

关键词： Fusion Reactor Nuclear Energy Progressive Thermalization Colliding Beams stellarator Mechanical Gain

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Proposal of a Deuterium-Deuterium Fusion/PWR Fission Hybrid Reactor

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World Journal of Nuclear Science and Technology 2024年第4期14卷 190-233页

作者： Patrick Lindecker Independent Researcher Paris France

This article proposes to associate a Deuterium-Deuterium (D-D) fusion reactor with a PWR (fission Pressurized Water Reactor) in a hybrid reactor. Even if the mechanical gain (Q factor) of the D-D fusion reactor is below the unity and consequently consumes more energy than it supplies, due to the high energy amplification factor of the PWR fission reactor, the global yield is widely superior to 1. As the energy supplied by the fusion reactor is relatively low and as the neutrons supplied are mainly issued from D-D fusions (at 2.45 MeV), the problems of heat flux and neutrons damage connected with materials, as with D-T fusion reactors are reduced. Of course, there is no need to produce Tritium with this D-D fusion reactor. This type of reactor is able to incinerate any mixture of natural Uranium, natural Thorium and depleted Uranium (waste issued from enrichment plants), with natural Thorium being the best choice. No enriched fuel is needed. So, this type of reactor could constitute a source of energy for several thousands of years because it is about 90 more efficient than a standard fission reactor, such as a PWR or a Candu one, by extracting almost completely the energy from the fertile materials U238 and Th232. For the fission part, PWR technology is mature. For the fusion part, it is based on a reasonable hypothesis done on present stellarators projects. The working of this reactor is continuous, 24 hours a day. In this paper, it will be targeted a reactor able to provide net electric power of about 1400 MWe, as a big fission power plant.

关键词： Fusion Reactor Fission Reactor Hybrid Reactor Nuclear Energy Deuterium-Deuterium Reactor Deuterium Colliding Beams Racetrack stellarator Power Plant PWR

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