FusionPapers
図版検索トレンドwiki日本の研究
© 2026 FUSIONPAPERS
About法務情報
ジャーナル一覧に戻る
Fusion Engineering and Design

Fusion Engineering and Design

An International Journal for Fusion Energy and Technology devoted to Experiments, Theory, Methods and Design

公式サイト

Impact Factor

1.7

Citescore

3.7

最新論文

  • Planar coil design for the Helios stellarator fusion power plant
  • Equilibrium optimization of the Helios planar coil stellarator power plant
  • Core profile prediction and transport analysis of the Helios stellarator fusion power plant
  • Superconducting planar coils for magnetic field shaping in the Helios Stellarator
  • Design of the superconducting encircling coils for Helios, the planar coil stellarator
AI解説分析論文一覧
全 15,241 件の論文
並び順:新しい順古い順被引用数順

Achieving effective bonding between W-75Cu composite and CuCrZr alloy via spark plasma sintering

Changcheng Sang, Dang Xu, Kaichao Fu, Ruizhi Chen, Jigui Cheng2025

A structural optimized method and verification of fusion converter for high current sharing performance

Zhongma Wang, Xingxing Shao, Jiameng Wu, Tao Xu, Yanchun Wang2025

High heat flux tests of tungsten – RAFM steel mock-up brazed by Ti-Zr-4Be alloy

D.M. Bachurina, A.N. Suchkov, O.N. Sevryukov, V.O. Kirillova, I.V. Mazul2025

Observation of greater blister skin thickness compared with the implantation depth of high-energy helium in tungsten

Yuki Uchida, Seiki Saito, Tsuneo Suzuki, Kazumasa Takahashi, Takashi Kikuchi2025

Effects of neutron irradiation on hydrogen isotope permeation on W-Re

Yuzuka Hoshino, Fei Sun, Makoto I. Kobayashi, Takeshi Toyama, Yasuhisa Oya2025

Simulation analysis of the motion accuracy of the ECRH launcher steering mechanism based on ADAMS

Xiaoguang Zhang, Nengtao Zhou, Haibiao Zhang, Dingzhen Li, Yunying Tang2025

Manufacturing and performance test of a 21.59 kA @77 K, self-field full-size REBCO-HFRC cable-in-conduit conductor

Haihong Liu, Huan Jin, Guanyu Xiao, Chuanyi Zhao, Jinggang Qin2025

Thermal hydraulic analysis on the heat transfer enhancement of the COOL blanket first wall for CFETR

Wei Feng, Kecheng Jiang, Lei Chen, Songlin Liu2025

Design of the in-VV LOCA experimental facility for CFETR water-cooled components

Qixin Ling, Kecheng Jiang, Qingzhu Liang, Lei Chen, Songlin Liu2025

Minimum quench energy analysis for Six-Around-One HTS cable-in-conduit conductor

Haihong Liu, Libiao Hu, Huan Jin, Rui Kang, Jinggang Qin2025

Validation of NSFsim as a Grad-Shafranov equilibrium solver at DIII-D

Randall Clark, Maxim Nurgaliev, Eduard Khairutdinov, Georgy Subbotin, Dmitri M. Orlov2025

Flow-solid-heat coupled analyses of scandium target for deuterium- deuterium neutron generator

Mengmeng Li, Yuzhong Qian, Zhenqing Zhu, Xin Tao, Chundong Hu2025

Thomson scattering diagnostics at the Globus-M2 tokamak

N.S. Zhiltsov, G.S. Kurskiev, S.Yu. Tolstyakov, V.A. Solovey, A.Yu. Yashin2025

Development of excitation controller for 300 MVA energy storage generator

Qiang Ye, Huajun Li, Weibin Li, Yingqiao Wang, Yang Ji2025

Thermal mechanical evaluation of candidate tokamak divertor elements informing fusion materials design windows

Spencer L. Thomas, Lance L. Snead, Brian D. Wirth, Jason R. Trelewicz2025

Thermal-hydraulic analysis of the ITER CCWS-1 cooling loop

Giuseppe Agnello, Andrea Ciampichetti, Giovanni Dell'Orco, Pietro Alessandro Di Maio, Eugenio Vallone2025

Influence of full-cycle heat treatment on microstructure and mechanical properties of CLF-1 steel

J.S. Wan, G.P. Yang, L.R. Liu, H.B. Liao, X.H. WU2025

Development of an infrared diagnostic system with multi-spectrum or high frame rate for measuring the synchrotron radiation emitted by runaway electrons on EAST

Yongkuan Zhang, Ruijie Zhou, Liqun Hu, Sensen Lin, Xiaofei Yang2025

Study on the changes in the reverse recovery characteristics of high-power thyristor under 14.1 MeV fusion neutron irradiation

Wei Tong, Hua Li, Dongmei Liu, Yanan Wu, Kun Wang2025

Physics and technology maturity level required for the K-DEMO design points

J.S. Kang, G. Jo, J-M. Kwon, B.G. Hong2025

Vacuum vessel design with lofted toroidal surfaces for a QHS configuration

John Schmitt, Dieter Boeyaert, Aaron Bader, Robert Davies, Jacob Nesbit2025

A review on irradiated beryllium and beryllium alloy for fusion reactor application: Microstructure evolution, properties changes, and fabrication

Tonghao Wang, Pingping Liu, Shujing Wang, Shuai Wang, Farong Wan2025

JET CODAS - the final status

John Waterhouse, Martin Wheatley, Adam Stephen, Colin Hogben, Paul McCullen2025

Corrigendum to “Development of double-walled bellows for ITER VUV spectrometer systems” [Fusion Engineering and Design 207 (2024) 114643]

Jaemin KIM, YoungHwa AN, SungMin JUNG, HongKiun LEE, MunSeong CHEON2025

Study and analysis of the design considerations for controlling vertical plasma position in ADITYA-U tokamak

Rohit Kumar, Harshita Raj, Vinay Menon, Deepti Sharma, Joydeep Ghosh2025

Novel high temperature tritium blanket designs for confined spaces in spherical tokamak fusion reactors

M.D. Anderton, C. Baus, T.P. Davis, R. Pearson, J. Hagues2025

Installation, thermal curing, qualification testing of divertor and position control coils in ADITYA-U tokamak

Rohit Kumar, Vaibhav Ranjan, Harshita Raj, Sharvil Patel, J. Ghosh2025

Effect of severe plastic deformation on surface modification of tungsten exposed to low energy helium ion irradiation

Yashan Guo, Ning Guo, Ao Zhang, Kemin Xue, Ping Li2025

The influence of nitrogen in shielding gas on the 316LN austenitic stainless steel welded joints

Zhongtao Zhang, Zhihong Liu, Jiefeng Wu, Jianguo Ma2025

Comparative analysis of neutronic features for various specimen payload configurations within the IFMIF-DONES HFTM

I. Álvarez, M. Anguiano, F. Mota, R. Hernández, D. Sosa2025
前へ1...29303132333435...509次へ