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  • Numerical investigation of hydrogen isotope retention by an yttrium pebble-bed from flowing liquid lithium
    Nucl. Fusion (IF 3.706) Pub Date : 2020-09-15
    S.J. Hendricks, E. Carella, C. Moreno and J. Molla

    Ensuring a secure and reliable execution of the International Fusion Materials Irradiation Facility (IFMIF) and the DEMO-Oriented Neutron Source (DONES) requires their liquid lithium loops to be purified from hydrogen isotopes which are generated during operation. For this purpose, an yttrium pebble-bed will serve as a hydrogen hot trap. Former intentions to predict the retention behavior of an yttrium

    更新日期:2020-09-16
  • Rapid tritium accounting method based on the temperature gradient for a tritium storage and delivery system: an interpretation with experiments
    Nucl. Fusion (IF 3.706) Pub Date : 2020-09-15
    Samuel Park, Jisoo Kim and Hyun-Goo Kang

    This paper proposes a rapid tritium accounting method that will enhance the tritium accountability of a tritium storage and delivery system (SDS) with in-bed calorimetry. We derive an accounting model with validation of assumptions based on the law of Newton’s cooling. The characteristics of the accounting model enable rapid accounting by instantly measuring the temperature gradient of a tritium storage

    更新日期:2020-09-16
  • Exposure of Indian RAFM under variation of He + flux and target emperature in the CIMPLE-PSI linear device
    Nucl. Fusion (IF 3.706) Pub Date : 2020-09-15
    Trinayan Sarmah, Pubali Dihingia, Mizanur Rahman, J. Ghosh, P. Chaudhuri, Divesh N. Srivastava, B. Satpati, Sanjiv Kumar, M. Kakati and G. De Temmerman

    The paper reports first investigations of the effect of low-temperature helium (He) plasma exposure on the India specific reduced activation ferritic martensitic (IN-RAFM) steel. Experiments are performed in the CIMPLE-PSI device, over the variation of ion-flux (∼3 × 10 22−23 m −2 s −1 ) and target temperature (316 K−830 K), for ion-fluence up to 1.6 × 10 26 m −2 . Strong morphology changes have been

    更新日期:2020-09-16
  • Kinetic model for hydrogen absorption in tungsten with coverage dependent surface mechanisms
    Nucl. Fusion (IF 3.706) Pub Date : 2020-09-15
    E.A. Hodille, S. Markelj, M. Pecovnik, M Ajmalghan, Z.A. Piazza, Y. Ferro, T. Schwarz-Selinger and C. Grisolia

    In this work, a kinetic model is presented to describe hydrogen absorption and desorption from tungsten at different surface coverages. Activation energies for hydrogen absorption into the bulk and desorption from the surface of tungsten are modelled by functions that depend explicitly and continuously on the hydrogen surface coverage. A steady-state model is developed to derive these activation energies

    更新日期:2020-09-16
  • Neutral impact on anomalous edge plasma transport and its correlation with divertor plasma detachment
    Nucl. Fusion (IF 3.706) Pub Date : 2020-09-13
    Yanzeng Zhang, Sergei I. Krasheninnikov, Rebecca Masline and Roman D. Smirnov

    The impact of neutrals on anomalous edge plasma transport and zonal flow (ZF) is considered. As an example, it is assumed that edge plasma turbulence is driven by the resistive drift wave (RDW) instability. It is found that the actual effect of neutrals is not related to a suppression of the instability per se , but due to an impact on the ZF. Particularly, it is shown that, whereas the neutrals make

    更新日期:2020-09-14
  • Hybrid simulations of reversed shear Alfvén eigenmodes and related nonlinear resonance with fast ions in a tokamak plasma
    Nucl. Fusion (IF 3.706) Pub Date : 2020-09-09
    Y.R. Yang, W. Chen, M.Y. Ye, J.B. Yuan and M. Xu

    Reversed shear Alfvén eigenmodes (RSAEs) are often observed in HL-2A reversed shear discharges with ##IMG## [http://ej.iop.org/images/0029-5515/60/10/106012/nfaba673ieqn1.gif] {$q_{\mathrm{min}}\ \sim\ 1$} . The modes are highly localized near ##IMG## [http://ej.iop.org/images/0029-5515/60/10/106012/nfaba673ieqn2.gif] {$q_{\mathrm{min}}$} , and their frequencies sweep downward or upward as ##IMG##

    更新日期:2020-09-10
  • First analysis of the misaligned leading edges of ITER-like plasma facing units using a very high resolution infrared camera in WEST
    Nucl. Fusion (IF 3.706) Pub Date : 2020-09-09
    A. Grosjean, Y. Corre, R. Dejarnac, J. Gaspar, J. P. Gunn, S. Carpentier-Chouchana, X. Courtois, E. Delmas, G. De Temmerman, M. Diez, L. Dubus, A. Durocher, F. Escourbiac, M. Firdaouss, J. Gerardin, M. Houry, R.A. Pitts, C. Pocheau, E. Tsitrone and the WEST team

    Twelve ITER-like plasma-facing units made of tungsten were exposed in the WEST tokamak divertor, with three plasma-facing units (PFUs) significantly overexposed to plasma heat flux: one sharp-edged PFU (vertical misalignment h = 0.8 mm) and two chamfered PFUs (h =0.6 mm and 0.3 mm, respectively). This paper describes the first temperature analysis obtained with a very high spatial resolution infrared

    更新日期:2020-09-10
  • Linear, resistive stability studies for Wendelstein 7-X-type equilibria with external current drive
    Nucl. Fusion (IF 3.706) Pub Date : 2020-09-07
    E. Strumberger, S. Günter and the Wendelstein 7-X team

    Comprehensive linear stability studies of resistive modes are presented for Wendelstein 7-X-type stellarator equilibria with electron cyclotron current drive (ECCD). The external co-current drive leads to an increase of the rotational transform and the formation of one or two ι = 1 rational flux surfaces. Using the 3D linear stability CASTOR3D code, low n * -type resistive modes ( n * = 1,2...,8 with

    更新日期:2020-09-08
  • Resolidification-controlled melt dynamics under fast transient tokamak plasma loads
    Nucl. Fusion (IF 3.706) Pub Date : 2020-09-07
    S. Ratynskaia, E. Thorén, P. Tolias, R. A. Pitts, K. Krieger, L. Vignitchouk, D. Iglesias, the ASDEX-Upgrade team, the JET contributors and the EUROfusion MST1 team

    Studies of macroscopic melt motion induced by fast transient power loads and the ensuing damage to plasma-facing components are critical for ITER. Based on state-of-the-art experiments, heat transfer is argued to be strongly entangled with fluid dynamics. The physics model of the MEMOS-U code is introduced. Simulations are reported of recent tokamak experiments concerning deliberate transient melting

    更新日期:2020-09-08
  • Hybrid simulation of fishbone instabilities with reversed safety factor profile
    Nucl. Fusion (IF 3.706) Pub Date : 2020-09-07
    Wei Shen, Feng Wang, G.Y. Fu, Liqing Xu and Zhenzhen Ren

    Linear stability and non-linear dynamics of the fishbone instabilities with reversed safety factor profile have been investigated by the global kinetic-magnetohydrodynamic (MHD) code M3D-K. For the consideration of the fishbone instability with a reversed q profile, there are two different types of the fishbone instability: dual resonant fishbone (DRF) with double q = 1 surfaces and non-resonant fishbone

    更新日期:2020-09-08
  • Measurements of plasma parameters in the divertor island of Wendelstein 7-X through line-ratio spectroscopy on helium
    Nucl. Fusion (IF 3.706) Pub Date : 2020-09-07
    T. Barbui, M. Krychowiak, O. Schmitz, S.A. Bozhenkov, E. Flom, G. Fuchert, C. Killer, R. König, M. Jakubowski, J.M. Muñoz Burgos, E. Pasch, E.R. Scott and W7-X team

    Electron temperature T e and density n e have been measured in the divertor island of Wendelstein 7-X by means of a new thermal He-beam system utilizing line-ratio spectroscopy. This system is equipped with a poloidal arrangement of five gas valves that allows to infer 2D plasma profiles T e ( R,Z ) and n e ( R,Z ) across the magnetic island forming the island divertor. A local maximum in T e ( R,Z

    更新日期:2020-09-08
  • Simulation of EAST edge plasma using SOLPS-ITER/BOUT++ coupling
    Nucl. Fusion (IF 3.706) Pub Date : 2020-09-07
    D.R. Zhang, Y.P. Chen, X.Q. Xu, T.Y. Xia, S.C. Liu and EAST team

    The self-consistent simulation of transport and turbulence in tokamak edge plasma on the EAST tokamak is performed by coupling the fluid plasma/neutral 2D transport code SOLPS-ITER and the fluid 3D turbulence code BOUT++. The convergence of the coupling is validated. The changing rates between the two consecutive profiles of density, electron temperature and ion temperature are close to zero in the

    更新日期:2020-09-08
  • Staged approach towards physics-based L-H transition models
    Nucl. Fusion (IF 3.706) Pub Date : 2020-09-07
    C. Bourdelle

    This article is the companion of an invited overview talk given at the H-Mode Workshop 2019. Quantitative predictions of the L to H power threshold are needed to prepare the ‘pre-nuclear’ ITER operation in H or He, as well as to design a future fusion reactor where the confinement regime interplay with divertor configuration, radiation level, etc has to be understood. With this urgency in mind, this

    更新日期:2020-09-08
  • Design of a PLD–grown Y 2 O 3 protective barrier for fusion relevant applications
    Nucl. Fusion (IF 3.706) Pub Date : 2020-09-07
    Boris Paladino, Matteo Vanazzi, Daniele Iadicicco, Andrea Perinot, Mario Caironi, Luca Ceseracciu, Pierfranco Reccagni, Serena Bassini, Marco Utili and Fabio Di Fonzo

    Advanced and innovative solutions are currently under investigations in order to solve the long-standing issues of materials constituting the breeding blanket of a future fusion reactor. Tritium permeation through steels, corrosion perpetrated by the breeding media, magnetohydrodynamic (MHD) effects and intense neutron irradiation hinder the realization of this technology. Recently, the employment

    更新日期:2020-09-08
  • Cause and impact of low-frequency chirping modes in DIII-D hybrid discharges
    Nucl. Fusion (IF 3.706) Pub Date : 2020-09-06
    D. Liu, W.W. Heidbrink, M. Podestà, Z.Z. Ren, L. Bardóczi, E.D. Fredrickson, G.Y. Fu, C.C. Petty, K.E. Thome, F. Turco and M.A. Van Zeeland

    Significant variations in MHD activity and fast-ion transport are observed in the DIII-D high-beta, steady-state hybrid discharges with a mixture of electron cyclotron (EC) waves and neutral beam injection (NBI). When electron cyclotron heating (ECH) or current drive (ECCD) is applied, Alfvén eigenmodes (AEs) are usually suppressed and replaced by low-frequency bursting modes. The analysis of a recently

    更新日期:2020-09-08
  • Magnetized directly-driven ICF capsules: increased instability growth from non-uniform laser drive
    Nucl. Fusion (IF 3.706) Pub Date : 2020-09-01
    C.A. Walsh, A.J. Crilly and J.P. Chittenden

    Simulations anticipate increased perturbation growth from non-uniform laser heating for magnetized direct-drive implosions. At the capsule pole, where the magnetic field is normal to the ablator surface, the field remains in the conduction zone and suppresses non-radial thermal conduction; in unmagnetized implosions this non-radial heat-flow is crucial in mitigating laser heating imbalances. Single-mode

    更新日期:2020-09-02
  • Geometric concepts for stellarator permanent magnet arrays
    Nucl. Fusion (IF 3.706) Pub Date : 2020-09-01
    K.C. Hammond, C. Zhu, T. Brown, K. Corrigan, D.A. Gates and M. Sibilia

    The development of stellarators that use permanent magnet arrays to shape their confining magnetic fields has been a topic of recent interest, but the requirements for how such magnets must be shaped, manufactured, and assembled remain to be determined. To address these open questions, we have performed a study of geometric concepts for magnet arrays with the aid of the newly developed Magpie code

    更新日期:2020-09-02
  • Experimental progress of hybrid operational scenario on EAST to kamak
    Nucl. Fusion (IF 3.706) Pub Date : 2020-09-01
    X. Gao, L. Zeng, M.Q. Wu, T. Zhang, Y. Yang, T.F. Ming, X. Zhu, Y.M. Wang, H.Q. Liu, Q. Zang, G.Q. Li, J. Huang, X.Z. Gong, Y.Y. Li, J.G. Li, Y.X. Wan and the EAST team

    Extensive experiments of advanced scenario development, which contribute to the ITER hybrid operational scenario have been carried out on experimental advanced superconducting tokamak (EAST) tokamak recently with the ITER-like tungsten divertor. The ##IMG## [http://ej.iop.org/images/0029-5515/60/10/102001/nfabaa91ieqn1.gif] {${\beta _N}$} in this operational scenario is intermediate up to 2.1 (EAST#78987

    更新日期:2020-09-02
  • Control of multi-helicity neo-classical tearing modes by electron cyclotron current drive in tokamak plasmas
    Nucl. Fusion (IF 3.706) Pub Date : 2020-09-01
    Tong Liu, Jialei Wang, Lai Wei and Zheng-Xiong Wang

    The effect of electron cyclotron current drive (ECCD) on the multi-helicity neo-classical tearing modes (2/1 and 3/2 NTMs) in tokamak plasmas is numerically studied by adopting a reduced magnetohydrodynamic (MHD) model. It is found that the control process of certain single helicity NTM by ECCD can be influenced by nonlinear multi-helicity interaction. In the case without plasma rotation, the ‘phase

    更新日期:2020-09-02
  • Parametric decay instabilities near the second-harmonic upper hybrid resonance in fusion plasmas
    Nucl. Fusion (IF 3.706) Pub Date : 2020-09-01
    S.K. Hansen, S.K. Nielsen, J. Stober, J. Rasmussen, M. Stejner, M. Hoelzl, T. Jensen and the ASDEX Upgrade team

    Parametric decay instabilities (PDIs) lead to the generation of strong frequency-shifted radiation when powerful X-mode polarized microwaves, injected for electron cyclotron resonance heating (ECRH) of fusion plasmas, cross a region of non-monotonic electron density near the second-harmonic upper hybrid resonance (UHR). For the standard second-harmonic X-mode ECRH scenarios used at the ASDEX Upgrade

    更新日期:2020-09-02
  • Plasma heating and generation of energetic D ions with the 3-ion ICRF + NBI scenario in mixed H-D plasmas at JET-ILW
    Nucl. Fusion (IF 3.706) Pub Date : 2020-09-01
    Ye.O. Kazakov, M. Nocente, M.J. Mantsinen, J. Ongena, Y. Baranov, T. Craciunescu, M. Dreval, R. Dumont, J. Eriksson, J. Garcia, L. Giacomelli, V.G. Kiptily, K.K. Kirov, L. Meneses, F. Nabais, M.F.F. Nave, M. Salewski, S.E. Sharapov, Ž. Štancar, J. Varje, H. Weisen and JET contributors

    Dedicated experiments were conducted in mixed H-D plasmas in JET to demonstrate the efficiency of the 3-ion ICRF scenario for plasma heating, relying on injected fast NBI ions as the resonant ion component. Strong core localization of the RF power deposition in the close vicinity of the ion-ion hybrid layer was achieved, resulting in an efficient plasma heating, generation of energetic D ions, strong

    更新日期:2020-09-02
  • Energetic particle transport and loss induced by helically-trapped energetic-ion-driven resistive interchange modes in the Large Helical Device
    Nucl. Fusion (IF 3.706) Pub Date : 2020-09-01
    K. Ogawa, M. Isobe, S. Sugiyama, H. Matsuura, D.A. Spong, H. Nuga, R. Seki, S. Kamio, Y. Fujiwara, H. Yamaguchi, M. Osakabe and LHD Experiment group

    In this work, energetic-ion confinement and loss due to energetic-ion driven magnetohydrodynamic modes are studied using comprehensive neutron diagnostics and orbit-following numerical simulations for the Large Helical Device (LHD). The neutron flux monitor is employed in order to obtain global confinement of energetic ions and two installed vertical neutron cameras (VNCs) viewing different poloidal

    更新日期:2020-09-02
  • Deuterium retention in solid and liquid tin after low-temperature plasma exposure
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-27
    A. Manhard, T. Schwarz-Selinger, M. Balden, T. Dürbeck, H. Maier and R. Neu

    Recently, plasma-facing components based on liquid metals were proposed for a prospective nuclear fusion reactor in order to circumvent challenges that occur for solid metal components, such as erosion lifetime, neutron embrittlement or transient overloading. One candidate material is liquid tin. We present a systematic study of the behavior of solid and liquid tin exposed to a low-temperature deuterium

    更新日期:2020-08-28
  • A simple analytic model of impurity leakage from the divertor and accumulation in the main scrape-off layer
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-27
    P.C. Stangeby and D. Moulton

    Edge codes such as SOLPS-ITER find distributions of impurity ions, e.g. of C, N, Ne and Ar, in the divertor and SOL which are quite non-uniform spatially, both poloidally and radially. Poloidally, impurity ion density distributions often have strong peaks near the targets as well as a peak on/near the separatrix in the main SOL near the outside midplane. A high density of low-Z impurities near the

    更新日期:2020-08-28
  • Stabilization of energetic-ion driven toroidal Alfvén eigenmode by energetic electrons in tokamak plasmas
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-27
    Jialei Wang, Yasushi Todo, Hao Wang, Zheng-Xiong Wang and Malik Idouakass

    Energetic electron effects on an energetic-ion driven toroidal Alfvén eigenmode (TAE) are investigated via hybrid simulations of an MHD fluid interacting with energetic particles. Both energetic electrons and energetic ions described by drift-kinetic equations are included in the present work. It is found that the TAE can be effectively stabilized by off-axis peaked energetic electrons which are located

    更新日期:2020-08-28
  • Topology optimization of permanent magnets for stellarators
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-27
    Caoxiang Zhu, Kenneth Hammond, Thomas Brown, David Gates, Michael Zarnstorff, Keith Corrigan, Marc Sibilia and Eliot Feibush

    We introduce a topology optimization method to design permanent magnets for advanced stellarators. Recent research shows that permanent magnets have great potential to simplify stellarator coils. We adopt state-of-the-art numerical techniques to determine the presence of magnets in the entire design space. The FAMUS code is developed and it can design engineering-feasible permanent magnets for general

    更新日期:2020-08-28
  • The impact of anisotropy on ITER scenarios
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-27
    M.J. Hole, Z. Qu, S. Pinches, M. Schneider, I.L. Arbina, M.J. Mantsinen and O. Sauter

    We report on the impact of anisotropy to tokamak plasma configuration and stability. Our focus is on analysis of the impact of anisotropy on ITER pre-fusion power operation 5 MA, B = 1.8 T ICRH scenarios. To model ITER scenarios remapping tools are developed to distinguish the impact of pressure anisotropy from the change in magnetic geometry caused by an anisotropy-modified current profile. The remappings

    更新日期:2020-08-28
  • Simulation of Alfvén eigenmodes destabilized by energetic electrons in tokamak plasmas
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-27
    Jialei Wang, Yasushi Todo, Hao Wang and Zheng-Xiong Wang

    Alfvén eigenmodes (AEs) driven by energetic electrons were investigated via hybrid simulations of an MHD fluid interacting with energetic electrons. The investigation focused on AEs with the toroidal number n = 4. Both energetic electrons with centrally peaked beta profile and off-axis peaked profile are considered. For the centrally peaked energetic electron beta profile case, a toroidal Alfvén eigenmode

    更新日期:2020-08-28
  • Excitation of the beta-induced Alfvén-acoustic eigenmode during sawtooth-like oscillation in EAST
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-27
    Ming Xu, H.L. Zhao, J.Z. Zhang, L.Q. Xu, H.Q. Liu, G.Q. Li, G.Q. Zhong, Q. Zang, L.Q. Hu, X.Z. Gong, G.S. Xu, X.D. Zhang, B.N. Wan and EAST team

    The characteristics and excitation conditions of the beta-induced Alfvén-acoustic eigenmode (BAAE) have been investigated during sawtooth-like oscillation in the Experimental Advanced Superconducting Tokamak (EAST). The sawtooth-like events are triggered periodically by the ##IMG## [http://ej.iop.org/images/0029-5515/60/11/112005/nfab7c2dieqn1.gif] {$m = 2/n = 1$} double-tearing reconnection crash

    更新日期:2020-08-28
  • Self-consistent modeling of runaway electron generation in massive gas injection scenarios in ASDEX Upgrade
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-27
    O. Linder, E. Fable, F. Jenko, G. Papp, G. Pautasso, the ASDEX Upgrade team and the EUROfusion MST1 team

    We present the first successful simulation of an induced disruption in ASDEX Upgrade from massive material injection (MMI) up to established runaway electron (RE) beam, thus covering pre-thermal quench, thermal quench and current quench (CQ) of the discharge. For future high-current fusion devices such as ITER, the successful suppression of REs, e.g. through MMI, is of critical importance to ensure

    更新日期:2020-08-28
  • Spatial channeling in toroidal plasmas: overview and new results
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-24
    Ya.I. Kolesnichenko, A.V. Tykhyy and R.B. White

    Energy and momentum transfer by eigenmodes in tokamaks and stellarators, which arises when eigenmodes are destabilized by superthermal ions in a region that does not coincide with the damping region, is considered. This phenomenon, named spatial channeling (SC), may play an important role in toroidal plasmas. It may affect plasma energy confinement, plasma rotation, heating of the electron and ion

    更新日期:2020-08-25
  • Resolving the fast ion distribution from imaging neutral particle analyzer measurements
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-24
    X.D. Du, M.A. Van Zeeland, W.W. Heidbrink, L. Stagner, A. Wingen, D. Lin and C.S. Collins

    A recently developed imaging neutral particle analyzer (INPA) on the DIII-D tokamak (Du 2018 Nucl. Fusion 58 082006) enables fast ion velocity-space tomography of high fidelity at the interrogated phase space. To accomplish this, the spatial and energy depending fast ( E < 80 keV) neutral flux towards the INPA stripping foils is calculated with FIDASIM and a newly developed code INPASIM simulates the

    更新日期:2020-08-25
  • Investigation of mode activity in NBI-heated experiments of Wendelstein 7-X
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-24
    C. Slaby, S. Äkäslompolo, M. Borchardt, J. Geiger, R. Kleiber, A. Könies, S. Bozhenkov, C. Brandt, A. Dinklage, M. Dreval, O. Ford, G. Fuchert, D. Hartmann, M. Hirsch, U. Höfel, Z. Huang, P. McNeely, N. Pablant, K. Rahbarnia, N. Rust, J. Schilling, A. von Stechow, H. Thomsen and the Wendelstein 7-X team

    The 2018 operation phase (OP 1.2b) of the stellarator Wendelstein 7-X (W7-X) included, for the first time, neutral beam injection (NBI) to heat the plasma. Since the injection geometry at W7-X is not parallel, this generates both passing and trapped fast particles. During longer phases of NBI injection, with the primary purpose to study the heating efficiency of this system, Alfvén eigenmodes (AEs)

    更新日期:2020-08-25
  • The systematic investigation of energetic-particle-driven geodesic acoustic mode channeling using MEGA code
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-24
    Hao Wang (王 灏), Yasushi Todo (藤堂 泰), Masaki Osakabe (長壁 正樹), Takeshi Ido (井戸 毅) and Yasuhiro Suzuki (鈴木 康浩)

    Energetic-particle-driven geodesic acoustic modes (EGAMs) channeling in the Large Helical Device (LHD) plasmas are systematically investigated for the first time using MEGA code. MEGA is a hybrid simulation code for energetic particles interacting with a magnetohydrodynamic (MHD) fluid. In the present work, both the energetic particles and the bulk ions are described kinetically. The EGAM profiles

    更新日期:2020-08-25
  • Summary of the 16th IAEA technical meeting on energetic particles in magnetic confinement systems—theory of plasma instabilities
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-24
    M. Barbarino, Y. Todo and M. Yagi

    This report summarizes the contributions presented at the 16th IAEA Technical Meeting on Energetic Particles in Magnetic Confinement Systems—Theory of Plasma Instabilities, held in Shizuoka, Japan, 3–6 September 2019. The meeting brought together about 100 experts from nuclear fusion research sites worldwide to discuss the physics of energetic particles and plasma instabilities, at the first joint

    更新日期:2020-08-25
  • Validation of the imaging neutral particle analyzer in nearly MHD quiescent plasmas using injected beam ions on DIII-D
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-24
    D.J. Lin, X.D. Du, W.W. Heidbrink and M.A. Van Zeeland

    The imaging neutral particle analyzer (INPA) is a scintillator-based diagnostic that provides energy and radially resolved measurements of confined fast ions. To verify operation, understanding and modeling of the diagnostic performance, distributions of deuterium beam ions in low density, nearly MHD-quiescent plasmas are measured on the DIII-D tokamak using the INPA. The distribution is altered by

    更新日期:2020-08-25
  • Observation of clump structure in transported particle orbit using an upgraded neutral particle analyzer during TAE burst in LHD
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-24
    S. Kamio, Y. Fujiwara, K. Nagaoka, K. Ogawa, R. Seki, H. Yamaguchi, H. Nuga, M. Isobe, M. Osakabe, C.Z. Cheng and the LHD Experiment Group

    Toroidal Alfvén eigenmode (TAE) bursts are often observed in relatively low-magnetic-field experiments in the Large Helical Device (LHD) with tangential nuclear beam injection. During TAE bursts, hole-clump pairs in real space were observed in previous studies. In order to observe the behavior of the energetic particles during TAE bursts in more detail, a tangential E-parallel-B-type neutral particle

    更新日期:2020-08-25
  • Excitation of elliptical and toroidal Alfvén eigenmodes by 3 He-ions of the MeV-energy range in hydrogen-rich JET plasmas
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-24
    V.G. Kiptily, Ye. Kazakov, M. Fitzgerald, M. Nocente, M. Iliasova, E. Khilkevich, M.J. Mantsinen, M.F.F. Nave, J. Ongena, S.E. Sharapov, A.E. Shevelev, Ž. Štancar, G. Szepesi, D.M.A. Taylor, Yu.V. Yakovenko and JET Contributors

    Elliptical (EAE) and toroidal Alfvén eigenmode (TAE) instabilities have been observed in hydrogen-rich JET discharges of the D- ( 3 He) -H ion cyclotron resonance heating (ICRH) scenario, which is characterized by strong absorption of radio frequency waves at very low concentrations of the resonant 3 He-ions. In the experiments, core localized TAEs with a frequency f TAE ≈ 280 kHz with mode numbers

    更新日期:2020-08-25
  • Peeling-ballooning stability of tokamak plasmas with applied 3D magnetic fields
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-23
    M.S. Anastopoulos Tzanis, C.J. Ham, Snyder P.B. and H.R. Wilson

    The poloidal harmonics of the toroidal normal modes of an unstable axisymmetric tokamak plasma are employed as basis functions for the minimisation of the 3D energy functional. This approach presents a natural extension of the perturbative method considered in Anastopoulos Tzanis et al (2019 Nucl. Fusion 59 126028). This variational formulation is applied to the stability of tokamak plasmas subject

    更新日期:2020-08-25
  • Efficient estimation of drift orbit island width for passing ions in a shaped tokamak plasma with a static magnetic perturbation
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-23
    Kouji Shinohara, Andreas Bierwage, Akinobu Matsuyama, Yasuhiro Suzuki, Go Matsunaga, Mitsuru Honda, Shuhei Sumida and Junghee Kim

    Non-axisymmetric magnetic perturbations contribute to the transport of fast ions in tokamaks. While knowledge of the perturbed magnetic topology suffices for characterizing the displacement of thermal particles (few keV), the trajectories of fast particles (0.1–few keV) vary depending on their charge, mass, kinetic energy and velocity pitch. The computational effort needed to follow the drift orbits

    更新日期:2020-08-25
  • Boron synergies in lithium film performance
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-23
    A. Devitre, E. Oyarzabal, I. Fernández-Berceruelo, D. Tafalla and F.L. Tabares

    Fusion experiments use lithium and boron getters to capture impurities and control the density of fuel species in the plasma. In the TJ-II Stellarator, the addition of a boron-carbon substrate was found to extend the lifetime of the very reactive lithium wall conditioning. However, the synergies between the lithium layer and the underlying boron-carbon, or the effect of a glow discharge cleaning, on

    更新日期:2020-08-24
  • Effects of triangularity on the fusion performance of CFETR
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-17
    Cheng-Xi Zhou, Jia-Le Chen, V.S. Chan, Xiang Jian, G. Zhuang, Yi-Ren Zhu and CFETR team

    An important task of the China Fusion Engineering Test Reactor physics design is to develop operation scenarios with high fusion power (1 GW), high bootstrap current fraction for steady-state and a plasma edge compatible with heat and particle exhaust. To achieve these goals, triangularity ( δ ) effects on the fusion performance of two candidate scenarios, with or without reversed magnetic shear (RS)

    更新日期:2020-08-18
  • Mixed hydrogen-deuterium plasmas on JET ILW
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-17
    D.B. King, E. Viezzer, I. Balboa, M. Baruzzo, E. Belonohy, J. Buchanan, I.S. Carvalho, K. Cave-Ayland, C.D. Challis, I. Coffey, E.G. Delabie, L. Garzotti, S. Hall, J.C. Hillesheim, L. Horvath, E. Joffrin, D. Keeling, K. Kirov, C.F. Maggi, M. Maslov, S. Saarelma, S. Silburn, E.R. Solano, D. Valcarcel, JET contributors and JET contributors

    A study of mixed hydrogen-deuterium H-mode plasmas has been carried out in JET-ILW to strengthen the physics basis for extrapolations to JET D-T operation and to support the development of strategies for isotope ratio control in future experiments. Variations of input power, gas fuelling and isotopic mixture were performed in H-mode plasmas of the same magnetic field, plasma current and divertor configuration

    更新日期:2020-08-18
  • Deuterium release from deuterium plasma-exposed neutron-irradiated and non-neutron-irradiated tungsten samples during annealing
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-17
    V.Kh. Alimov, Y. Hatano, T. Kuwabara, T. Toyama, Y. Someya and A.V. Spitsyn

    We examine the effect of neutron irradiation on the release of deuterium from tungsten at 573 K to understand the efficiency of tritium removal by baking out at moderate temperatures. Tungsten samples, undamaged and neutron-irradiated to a damage level of approximately 0.016 displacements per atom, are exposed to low-energy (108 eV), high-flux (3.0 × 10 21 to 9.4 × 10 21 m −2 s −1 ) deuterium plasma

    更新日期:2020-08-18
  • Avalanche electron heat transport events triggered by non-linear mode couplings in HL-2A neutral beam injection heated L-mode plasmas
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-17
    W. Chen, Z.B. Shi, Z.Y. Qiu, L.M. Yu, P.W. Shi, M. Jiang, X.Q. Ji, Y.G. Li, X.X. He, K.R. Fang, Y.P. Zou, R.R. Ma, X.L. Zhu, W.L. Zhong, X.T. Ding, Q.W. Yang, Z.X. Wang, J.Q. Li, M. Xu and X.R. Duan

    Understanding cross-field anomalous transport is a central issue in the magnetic confinement fusion research. Recently, a long range large avalanche electron heat transport event has been observed in HL-2A neutral beam injection heated low-confinement mode (L-mode) plasmas. It is found and identified firstly that the non-linear mode couplings between high-frequency core-localized toroidal Alfvén eigenmodes

    更新日期:2020-08-18
  • Fishbone instability driven by trapped fast ions in a toroidal plasma with reversed magnetic shear
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-13
    Yutian Miao, G.Z. Hao, H.D. He, M.J. Hole, F. Porcelli, Z.S. Qu, Yue Liu, S. Wang, G.Q. Dong, W. Chen, H.T. Chen, Y.Q. Wang, Q.D. Gao, A.K. Wang and M. Xu

    Based on the non-perturbative approach, the hybrid code MARS-K is applied to study fishbone (FB) instabilities driven by trapped fast ions in a toroidal plasma with q profile nearly being flat or non-monotonic. We explore the dependency of the FB with variation in the fast ion distribution, thermal particle kinetic effects, safety factor ( q ) profile and plasma resistivity. When the safety factor

    更新日期:2020-08-14
  • Localizing resonant magnetic perturbations for edge localized mode control in KSTAR
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-13
    S.M. Yang, J.-K. Park, N.C. Logan, C. Zhu, Q. Hu, Y.M. Jeon, Y. In, W.H. Ko, S.K. Kim, Y.H. Lee and Y.S. Na

    An external 3D magnetic perturbation typically drives a resonant response at the rational surfaces from the core to the edge of tokamak plasmas, due to strong mode coupling and amplification. This paper presents a method to isolate the edge from core resonant fields using the ideal perturbed equilibrium code and to design an edge-localized resonant magnetic perturbation (RMP) for effective edge localized

    更新日期:2020-08-14
  • The performance of first CORC cable solenoid insert for development of CFETR high-field magnet
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-13
    H. Jin, J.G. Qin, C. Zhou, H.J. Liu, F. Liu, P. Gao, G.Y. Xiao, H.J. Ma, J.G. Li, Y. Wu, D.H. Jiang, K.H. Wu, T. Ma, Y.F. Tan and J.J. Li

    A ReBCO coated conductor maintains high current-carrying capability under a high magnetic field and superior mechanical performance. As a promising candidate material for high-field high-temperature superconductor magnets, it has been designed for application in the China Fusion Engineering Test Reactor CS coil, with a maximum magnetic field requirement higher than 17 T. In practical application of

    更新日期:2020-08-14
  • Modeling plasma toroidal flow profile control via NTV torque with n = 2 3D fields in MAST-U
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-13
    Yueqiang Liu, A. Kirk, B.C. Lyons, S. Munarretto, C. Paz-Soldan, L. Piron and A.D. Turnbull

    Toroidal modeling utilizing the MARS-Q code (Liu et al 2013 Phys. Plasmas 20 042503) shows that large (compared to electromagnetic torque) neoclassical toroidal viscous (NTV) torque can be achieved in the plasma core region in reference MAST(-U) L-mode plasmas, by applying the n = 2 ( n is the toroidal mode number) 3D fields generated by the magnetic coils used for controlling the edge localized mode

    更新日期:2020-08-14
  • Generation of localized lower-hybrid current drive by temperature perturbations
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-13
    S.J. Frank, A.H. Reiman, N.J. Fisch and P.T. Bonoli

    Despite high demonstrated efficiency, lower-hybrid current drive (LHCD) has not been considered localized enough for neoclassical tearing mode (NTM) stabilization in tokamaks. This assessment must be reconsidered in view of the radiofrequency current condensation effect. We show that an island with a central hot spot induces significant localization of LHCD. Furthermore, in steady state tokamaks where

    更新日期:2020-08-14
  • Summary report of the 3rd IAEA technical meeting on fusion data processing validation and analysis (FDPVA)
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-13
    D. Mazon, S.M. Gonzalez de Vicente, M. Churchill, A. Dinklage, R. Fischer, M. Jakubowski, A. Murari, M. Romanelli, J. Vega, G. Verdoolaege and M. Xu

    The Third IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis took place at the IAEA Headquarters in Vienna, Austria, from 28–31 May and brought together more than 60 scientists and engineers from 19 Member States, the European Commission and ITER Organisation working on data analysis and machine learning (ML) methods for the processing of fusion data, collected either from experimental

    更新日期:2020-08-14
  • Runaway electron synchrotron radiation in a vertically translated plasma
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-13
    M. Hoppe, G. Papp, T. Wijkamp, A. Perek, J. Decker, B. Duval, O. Embreus, T. Fülöp, U.A. Sheikh, the TCV team and the EUROfusion MST1 team

    Synchrotron radiation observed from runaway electrons (REs) in tokamaks depends upon the position and size of the RE beam, the RE energy and pitch distributions, as well as the location of the observer. We show experimental synchrotron images of a vertically moving RE beam sweeping past the detector in the Tokamak à Configuration Variable (TCV) tokamak and compare it with predictions from the synthetic

    更新日期:2020-08-14
  • Angular momentum and rotational energy of mean flows in toroidal magnetic fields
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-13
    M. Wiesenberger and M. Held

    We derive the balance equation for the Favre averaged angular momentum in toroidal not necessarily axisymmetric magnetic field equilibria. We find that the components of angular momentum are given by the covariant poloidal and toroidal components of ##IMG## [http://ej.iop.org/images/0029-5515/60/9/096018/nfab9fa8ieqn1.gif] {$\boldsymbol{E}\times\boldsymbol{B}\ $} and parallel flow velocities and we

    更新日期:2020-08-14
  • Conservative discontinuous Galerkin scheme of a gyro-averaged Dougherty collision operator
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-13
    M. Francisquez, T.N. Bernard, N.R. Mandell, G.W. Hammett and A. Hakim

    A conservative discontinuous Galerkin scheme for a non-linear Dougherty collision operator in full- f long-wavelength gyrokinetics is presented. Analytically this model operator has the advective-diffusive form of Fokker-Planck operators, it has a non-decreasing entropy functional, and conserves particles, momentum and energy. Discretely these conservative properties are maintained exactly as well

    更新日期:2020-08-14
  • Reassessment of steady-state operation in ITER with NBI and EC heating and current drive
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-11
    A.R. Polevoi, A.A. Ivanov, S.Yu. Medvedev, G.T.A. Huijsmans, S.H. Kim, A. Loarte, E. Fable and A.Y. Kuyanov

    One of the three goals of the ITER project is to demonstrate fusion gain Q ≥ 5 in steady-state operation (SSO). A reassessment of the necessary conditions for Q ≥ 5 SSO in ITER has been carried out for steady-state scenarios assuming no internal transport barrier in the core plasma and with the sole use of neutral beam injection (NBI) and electron cyclotron heating and current drive (EC H&CD) as heating

    更新日期:2020-08-12
  • Pulsed-power-driven cylindrical aluminium liner implosions with a high aspect ratio at an 8 MA facility
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-11
    J. Lu, X.S. Yan, S.J. Meng, J.M. Ning, S.Q. Jiang, F.X. Chen, Z.C. Huang, R.H. Yang, F. Ye, R.K. Xu, Z.P. Xu and Z.H. Li

    First experimental investigations of foil aluminium liner implosions with a high aspect ratio of ∼ 10 3 at an 8 MA pulsed-power facility in China, motivated by possible application for magneto-inertial fusion, will be reported. Key diagnostics including UV cameras, micro-magnetic probes and x-ray pinhole imaging systems were fielded. Quasi-monochromatic UV images and optical streak data showed localized

    更新日期:2020-08-12
  • Power balance investigation in long-pulse high-performance discharges with ITER-like tungsten divertor on EAST
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-09
    Y. K. Liu, X. Gao, K. Hanada, Y. W. Yu, H. Q. Liu, L. Yang, T. Zhang, Y. X. Jie, J. P. Qian, L. Zeng, T. F. Ming, X. J. Liu, S. C. Liu, T. J. Xu, Y. Chen, Q. Zhuang, Y. L. Li, K. F. Gan, B. Zhang, M. W. Chen, P. F. Zi, Y. M. Wang, G. S. Li, K. Z. Zhu, T. Zhou, L. Li, L. Cao, X. Z. Gong, D. M. Yao, K. Wang, L. Wang, J.G. Li and the EAST Team

    The Experimental Advanced Superconducting Tokamak (EAST) research program concentrates on demonstrating steady-state high-performance H-mode operations with ITER-like tungsten divertor. Calorimetry was applied to actively water-cool the plasma facing components (PFCs) by increasing the water temperature for power balance investigation. Considering the energy balance of EAST long-pulse high-performance

    更新日期:2020-08-10
  • Toroidicity effects on the absorption of IC waves by electrons
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-09
    M. Brambilla and R. Bilato

    Poloidal modulation of the parallel velocity of charged particles in a tokamak magnetic field modifies the strength of electron absorption of the compressional wave in the ion cyclotron range of frequencies. We have developed a model of this effect which is sufficiently simple to be numerically tractable, and we have implemented it in TORIC full-wave code, which solves the wave equation in toroidal

    更新日期:2020-08-10
  • Toroidal modelling of core plasma flow damping by RMP fields in hybrid discharge on ASDEX upgrade
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-09
    N. Zhang, Y.Q. Liu, P. Piovesan, V. Igochine, D.L. Yu, S. Wang, G.Q. Dong, G.Z. Hao, G.L. Xia, W.J. Chen, L. Liu, J.Q. Li, X. Bai, The HL-2A Team, The ASDEX Upgrade Team and The EUROfusion MST1 Team

    In ASDEX Upgrade hybrid discharges, it is found that an externally applied n = 1 field preferentially distorts the plasma in the core, leading to significant flow damping there and elsewhere across the plasma radius. MARS-F/Q modeling of a neoclassical toroidal viscous NTV) torque that results from an amplified internal kink-type displacement in the plasma core is qualitatively consistent with the

    更新日期:2020-08-10
  • Highly porous tungsten for plasma-facing applications in nuclear fusion power plants: a computational analysis of hollow nanoparticles
    Nucl. Fusion (IF 3.706) Pub Date : 2020-08-06
    Pablo Díaz-Rodríguez, Francisco Munoz, José Rogan, Ignacio Martín-Bragado, J.M. Perlado, Ovidio Peña-Rodríguez, Antonio Rivera and Felipe J. Valencia

    Plasma-facing materials (PFMs) for nuclear fusion, either in inertial confinement fusion (ICF) or in magnetic confinement fusion (MCF) approaches, must withstand extremely hostile irradiation conditions. Mitigation strategies are plausible in some cases, but usually the best, or even the only, solution for feasible plant designs is to rely on PFMs able to tolerate these irradiation conditions. Unfortunately

    更新日期:2020-08-10
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