FusionPapers
図版検索AI要約wiki日本の研究装置ジャーナルChatGPTAbout
© 2026 FUSIONPAPERS
About法務情報
ジャーナル一覧に戻る
Nuclear Fusion

Nuclear Fusion

Nuclear Fusion is the acknowledged world-leading journal specializing in fusion. The journal covers all aspects of research, theoretical and practical, relevant to controlled thermonuclear fusion.

公式サイト

Impact Factor

3

Citescore

3.2

最新論文

  • Current ramp-up studies for NSTX-U in support of the development of non-inductive current ramp-up scenarios in STs
  • The impact of kinetic and global effects on ideal ballooning 2nd stable pedestals of conventional and low aspect-ratio tokamaks
  • Boundary turbulence simulations of the optimized HSX stellarator and comparison with experiments
  • Enabling integrated AI control on DIII-D: a control system design with state-of-the-art experiments
  • Ex situ investigation of boron, hydrogen, and oxygen distributions on W7-X divertor surfaces using picosecond-LIBS under vacuum
AI解説分析論文一覧
全 13,618 件の論文
並び順:新しい順古い順被引用数順

Determination of the characteristic magnetic pre-sheath length at divertor surfaces using micro-engineered targets on DiMES at DIII-D

S. Abe, C.H. Skinner, I. Bykov, Y.W. Yeh, A. Lasa, J. Coburn, D.L. Rudakov, C.J. Lasnier, H.Q. Wang, A.G. McLean2022被引用: 4

Dynamics of electron internal transport barrier formation at the H–L transition on EAST

X. Han, Y. Liu, T.F. Zhou, T. Zhang, T.H. Shi, Y.Y. Li, Y. Yuan, S.T. Mao, Y.F. Jin, X.H. Wu2022被引用: 3

Parallel flow driven by electron cyclotron heating in the helically symmetric experiment

Y. Yamamoto, S. Murakami, C.C. Chang, S.T.A. Kumar, J.N. Talmadge, K.M. Likin, D.T. Anderson2022

Anomalous tungsten transport driven by ion temperature gradient turbulence

Shaokang Xu, S. Maeyama, T.-H. Watanabe2022被引用: 2

Fast-ion-driven vertical modes in magnetically confined toroidal plasmas

T. Barberis, F. Porcelli, A. Yolbarsop2022被引用: 8

In situ measurements of low energy D plasma-driven permeation through He pre-damaged W

Xue-Chun Li, Hai-Shan Zhou, Hao-Dong Liu, Lu Wang, Guang-Nan Luo2022被引用: 5

Explaining the lack of power degradation of energy confinement in wide pedestal quiescent H-modes via transport modeling

Saeid Houshmandyar, K.H. Burrell, B.A. Grierson, J. McClenaghan, G.M. Staebler, C. Chrystal, M.R. Halfmoon, D.R. Hatch, L. Zeng, M.E. Austin2022被引用: 1

Non-axisymmetric MHD simulations of the current quench phase of ITER mitigated disruptions

F.J. Artola, A. Loarte, M. Hoelzl, M. Lehnen, N. Schwarz, the JOREK Team2022被引用: 15

Production and transport modelling of Po-210 in DEMO reactor

P. Chiovaro, A. Quartararo, S. Basile, S. Ciattaglia, P.A. Di Maio, F. Moro, I. Moscato, G.A. Spagnuolo2022被引用: 1

SOLPS-ITER analysis of drift effects on plasma profiles in the EAST scrape-off layer

Fuqiong Wang, Y. Liang, X.J. Zha, F.C. Zhong, S.T. Mao, Y.M. Duan, L.Q. Hu, L. Wang, J.B. Liu, N. Yan2022被引用: 4

Current drive experiments in SST1 tokamak with lower hybrid waves

P.K. Sharma, D. Raju, S.K. Pathak, R. Srinivasan, K.K. Ambulkar, P.R. Parmar, C.G. Virani, J. Kumar, S. Sharma, C. Singh2022被引用: 2

Influence of low-Z impurity on the stabilization of m/n= 2/1 tearing/locked modes in EAST

Ming Xu, Yunfeng Liang, Lai Wei, Yanmin Duan, Tonghui Shi, Hailin Zhao, Liqing Xu, Ruijie Zhou, Ling Zhang, Shuai Gu2022被引用: 4

Prevention of electron cyclotron current drive triggering explosive bursts in reversed magnetic shear tokamak plasmas for disruption avoidance

Tong Liu, Zheng-Xiong Wang, Lai Wei, Jialei Wang2022被引用: 7

Disruptive neoclassical tearing mode seeding in DIII-D with implications for ITER

R.J. La Haye, C. Chrystal, E.J. Strait, J.D. Callen, C.C. Hegna, E.C. Howell, M. Okabayashi, R.S. Wilcox2022被引用: 11

Challenges toward improvement of deuterium-injection power in the Large Helical Device negative-ion-based NBIs

K. Tsumori, K. Ikeda, M. Kisaki, H. Nakano, K. Nagaoka, Y. Fujiwara, S. Kamio, M. Osakabe2022被引用: 9

Predictions of radiation pattern and in–out asymmetries in the DEMO scrape-off layer using fluid neutrals

L. Aho-Mantila, F. Subba, M. Bernert, D.P. Coster, S. Wiesen, M. Wischmeier, X. Bonnin, S. Brezinsek, P. David, F. Militello2022被引用: 4

DC performance and AC loss of sub-size MgB2 CICC conductor for fusion magnet application

P. Gao, Y.X. He, H.J. Ma, V.A. Anvar, J.F. Huang, X.F. Pan, C. Zhou, A. Nijhuis, J.G. Li, J.G. Qin2022被引用: 3

Effects of alpha particles on the CTEM driven zonal flow in deuterium–tritium tokamak plasmas

M. S. Hussain, Weixin Guo, Lu Wang2022被引用: 2

The role of defects, deuterium, and surface morphology on the optical response of beryllium

M. Minissale, C. Louis De Canonville, C. Pardanaud, B. Butoi, R. Bisson, L. Gallais2022被引用: 4

Progress on neutronic analysis for CFETR

Peng Lu, Qiuran Wu, Hua Du, Yu Zheng, Xiaokang Zhang, Qingjun Zhu, Xuebin Ma, Songlin Liu2022被引用: 3

First plasma exposure of a pre-damaged ITER-like plasma-facing unit in the WEST tokamak: procedure for the PFU preparation and lessons learned

Marianne Richou, Yann Corre, Thorsten Loewenhoff, Mathilde Diez, Céline Martin, Anke Aretz, Jann Willem Coenen, Mehdi Firdaouss, Gregory Giacometti, Alex Grosjean2022被引用: 5

Cross-code comparison of the edge codes SOLPS-ITER, SOLEDGE2D and UEDGE in modelling a low-power scenario in the DTT

M. Moscheni, C. Meineri, M. Wigram, C. Carati, E. De Marchi, M. Greenwald, P. Innocente, B. LaBombard, F. Subba, H. Wu2022被引用: 8

Deconvolving the roles of E × B shear and pedestal structure in the energy confinement quality of super H-mode experiments

A.M. Garofalo, S. Ding, W.M. Solomon, B.A. Grierson, X. Jian, T.H. Osborne, C. Holland, M. Knolker, F.M. Laggner, C. Chrystal2022被引用: 3

Quantification of the effect of uncertainty on impurity migration in PISCES-A simulated with GITR

T.R. Younkin, K. Sargsyan, T. Casey, H.N. Najm, J.M. Canik, D.L. Green, R.P. Doerner, D. Nishijima, M. Baldwin, J. Drobny2022被引用: 3

Confinement improvement during detached phase with RMP application in deuterium plasmas of LHD

M. Kobayashi, R. Seki, Y. Hayashi, T. Oishi, K. Tanaka, Y. Takemura, K. Ida, T. Kinoshita, K. Mukai, S. Morita2022被引用: 3

Role of E × B drift in double-peak density distribution for the new lower tungsten divertor with unfavorable Bt on EAST

Guozhang Jia, Huiqian Wang, Guosheng Xu, Liang Wang, Ang Li, Rui Ding, Xiaoju Liu, Hang Si, Qingquan Yang, Yuqiang Tao2022被引用: 9

In situ leading-edge-induced damages of melting and cracking W/Cu monoblocks as divertor target during long-term operations in EAST

Dahuan Zhu, Changjun Li, Binfu Gao, Rui Ding, Baoguo Wang, Zongxiao Guo, Chuannan Xuan, Baixue Yu, Yang Lei, Junling Chen2022被引用: 10

Prediction of divertor heat flux width for ITER pre-fusion power operation using BOUT++ transport code

X.X. He, X.Q. Xu, Z.Y. Li, B. Zhu, Y. Liu2022被引用: 3

Hybrid simulations of beta-induced Alfvén eigenmode with reversed safety factor profile

Sizhe Duan, G.Y. Fu, Huishan Cai, Ding Li2022

Alfvén cascade eigenmodes above the TAE-frequency and localization of Alfvén modes in D–3He plasmas on JET

M. Dreval, S.E. Sharapov, Ye.O. Kazakov, J. Ongena, M. Nocente, R. Calado, R. Coelho, J. Ferreira, A. Figueiredo, M. Fitzgerald2022被引用: 10
前へ1...68697071727374...454次へ