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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

  • Corrigendum to “Improving the Newton cooling model to drive the optimization method for heterogeneous storage of ECRH hot data” [Fusion Engineering and Design 215 (2026) 115715]
  • Corrigendum to “Relativistic effects on stopping power of plasmas with heavy ions” [Fusion Engineering and Design 205 (2024), 114524]
  • Corrigendum to “Initial accident scenario analysis in support of a preliminary DEMO tritium plant design” [Fusion Engineering and Design 189 (2023) 113482]
  • Thermal behaviour of ZrCo getter beds during hydrogen absorption at variable flow rates and concentrations
  • Performance of the W7-X ECRH gyrotron diamond output window at 2 MW operation
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全 15,142 件の論文
並び順:新しい順古い順被引用数順

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. Trelewicz
2025

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

Development of a heated liquid Sn flowing system and preliminary results of wettability improvement by inter-metallic layer

Yukinori Hamaji, Yuki Hayashi, Suguru Masuzaki2025

Nuclear data uncertainty in 14C production from oxygen isotopes

Priti Kanth, Ivan Kodeli, Mark R. Gilbert2025

Performance of the insulation mock-up used alumino-silicate fiber composite for Bi-2212 Cable-in-Conduit Conductor

Jing Sun, Zhaohui Yan, Xin Luo, Jiefeng Wu, Zhihong Liu2025

Research and development on vanadium alloys for fusion breeder blanket application

Louis Butt, Alexandra Dickinson-Lomas, Martin Freer, Joven Lim, Yu-Lung Chiu2025

Strength analysis of the Upper Vertical Neutron Camera diagnostic system of the ITER Tokamak Upper Port # 18 under electromagnetic, hydraulic, thermal, and seismic loads

D.B. Gin, B. Coriton, F. Josseaume, S. Pak, J. Kim2025

Formation, characterization and deuterium permeation of Al2O3/Fe-Al layers on SS-316L surface

Feilong Yang, Xin Xiang, Chang'an Chen, Li Hu, Yaqi Song2024

Numerical study of dynamic behavior of beryllium pebble under perturbation of electromagnetic field in fusion blanket

Wang Jian, Tang Zhengquan, Liu Mingzong, Lei Mingzhun, Deng Haishun2024

Performances of three atmospheric dispersion models in predicting near-surface tritium concentration distribution

Yiling Ran, Yuxuan Wang, Baojie Nie, Chunlei Su, Dezhong Wang2024

Neutron transport and activation comparison between OpenMC and FISPACT-II in ARC-class reactor

Davide Pettinari, Raffaella Testoni, Massimo Zucchetti, Miriam Parisi2024
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