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Proposal of a Deuterium-Deuterium Fusion/PWR Fission Hybrid Reactor: 《World Journal of Nuclear Science and Technology》2024年第4期190-233,共44页Patrick Lindecker; 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 bel...; 关键词：Fusion Reactor Fission Reactor Hybrid Reactor Nuclear Energy Deuterium-Deuterium Reactor DEUTERIUM Colliding Beams Racetrack STELLARATOR Power Plant PWR

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12-22,共11页刘亿卓行郑平卫龚学余尹岚陈小昌钟翊君杨文军; supported by the National Key Research and Development Program of China(Nos.2022YFE03070000 and 2022YFE03070003);National Natural Science Foundation of China(Nos.12375220 and 12075114)。; 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 stellarator...; 关键词：spherical torus STELLARATOR electron cyclotron wave START-UP 0D model

Proposal of a Deuterium-Deuterium Fusion Reactor Intended for a Large Power Plant: 《World Journal of Nuclear Science and Technology》2024年第1期1-58,共58页Patrick Lindecker; This article looks for the necessary conditions to use Deuterium-Deuterium (D-D) fusion for a large power plant. At the moment, for nearly all the projects (JET, ITER…) only the Deuterium-Tritium (D-T) fuel is consid...; 关键词：Fusion Reactor Deuterium-Deuterium Reactor Catalyzed D-D Colliding Beams Stellarator Reactor Power Plant

A promising approach to steady-state fusion: High-temperature superconducting strong-field stellarator with precise omnigenity: 《The Innovation》2024年第1期23-25,共3页Guosheng Xu Zhiyuan Lu Dehong Chen Baonian Wan; This work was supported by the National Magnetic Confinement Fusion Energy Program of China(grant no.2019YFE03030000).; The stellarator has inherent advantages over the tokamak in achieving steady-state operation,especially due to its absence of disruptions and lack of need for current drive and the associated recirculating power.In re...; 关键词：FIELD APPROACH PRECISE

Progressive Thermalization Fusion Reactor Able to Produce Nuclear Fusions at Higher Mechanical Gain: 《Energy and Power Engineering》2022年第1期35-100,共66页Patrick Lindecker; 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 ...; 关键词：Fusion Reactor Nuclear Energy Progressive Thermalization Colliding Beams STELLARATOR Mechanical Gain

Investigation of turbulence rotation in the SOL and plasma edge of W7-X for different magnetic configurations: 《Plasma Science and Technology》2020年第6期21-31,共11页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; funding from the Euratom research and training program 2014-2018 and2019-2020 under grant agreement no.633053。; The W7-X stellarator is optimized with respect to neoclassical transport.Therefore turbulent transport plays an important role.It is equipped with an inertial cooled graphite divertor which intersects the island chain...; 关键词：STELLARATOR correlation reflectometer turbulence rotation scrape-off layer island divertor

A general comparison between tokamak and stellarator plasmas被引量：4: 《Matter and Radiation at Extremes》2016年第4期192-200,共9页Yuhong Xu; This paper generally compares the essential features between tokamaks and stellarators,based on previous review work individually made by authors on several specific topics,such as theories,bulk plasma transport and e...; 关键词：TOKAMAKS STELLARATORS Magnetohydrodynamic(MHD) Plasma transport and confinement DIVERTOR

The Parameters of the Stellarator as a Neutron Source for a Subcritical Reactor: 《Journal of Physical Science and Application》2014年第2期90-99,共10页Vasiliy Rudakov; 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 desi...; 关键词：STELLARATOR subcritical reactor ambipolar electric field neoclassical transport neutron source fusion power

Contribution of the Large Helical Device Plasmas to Alfvén Eigenmode Physics in Toroidal Plasmas被引量：1: 《Plasma Science and Technology》2009年第4期377-380,共4页K. TOI M. ISOBE M. OSAKABE F. WATANABE K. OGAWA T. TOKUZAWA A. SHIMIZU T. IDO K. IDA, T. ITO S. MORITA K. NAGAOKA K. NARIHARA M. NISHIURA S. OHDACHI S. SAKAKIBARA K. TANAKA LHD Experiment Group; LHD project budget of Japan (NIFS08ULHH508);the Grant-in-aid for Scientific Research from MEST of Japan (No.16082209);the JSPS-CAS Core-University Program in the field of Plasma and Nuclear Fusion; In the large helical device （LHD） having three dimensional configuration, Alfven eigenmodes （AEs） destabilized by energetic ions are widely investigated using neutral beam heated plasmas with monotonic and non-mon...; 关键词：alpha particles Alfven eigenmodes geodesic acoustic mode helical/stellarator

ICRF Heated Long-Pulse Plasma Discharges in LHD被引量：11: 《Plasma Science and Technology》2006年第1期28-32,共5页R. KUMAZAWA T. SEKI T. MUTOH K. SAITO T. WATARI Y. NAKAMURA M. SAKAMOTO T. WATANABE S. KUBO T. SHIMOZUMA Y. YOSHIMURA H. IGAMI Y. TAKEIRI Y. OKA K. TSUMORI M. OSAKABE K. IKEDA K. NAGAOKA O. KANEKO J. MIYAZAWA S. MORITA K. NARIHARA M. SHOJI S. MASUZAKI M. GOTO T. MORISAKI B. J. PETERSON K. SATO T. TOKUZAWA N. ASHIKAWA K. NISHIMURA H. FUNABA H. CHIKARAISHI T. NOTAKE Y. TORII H. OKADA M. ICHIMURA H. HIGAKI Y. TAKASE H. KASAHARA F. SHIMPO G.NOMURA C.TAKAHASHI M.YOKOTA A. KATO 赵燕平 J. S. YOON J. G. KWAK H. YAMADA K. KAWAHATA N. OHYABU K. IDA Y. NAGAYAMA N. NODA A. KOMORI S. SUDO O. MOTOJIMA; supported in part by the JSPS-CAS Core-University Program in the field of Plasma and Nuclear Fusion; A long-pulse plasma discharge for more than 30 min. was achieved on the Large Helical Device （LHD）. A plasma of ne = 0.8 × 10^19 m^-3 and T10 = 2.0 keV was sustained with PICH = 0.52 MW, PECH = 0.1 MW and averaged ...; 关键词：helical/stellarator configuration ICRF heating steady state operation

STELLARATOR