図版検索 AI要約 wiki 日本の研究装置ジャーナル ChatGPT About

© 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

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

AI解説分析論文一覧

キーワード検索

年

AI要約

全 15,142 件の論文

並び順:新しい順古い順被引用数順

Fabrication of a thick copper-stainless steel clad plate for nuclear fusion equipment by explosive welding

Yuxin Wang, Xiaojie Li, Xiaohong Wang, Honghao Yan2018

Evaluation of the boundary of the vacuum in a Tokamak

Y. Wang, M. Tadi2018

Microstructural characterization and strengthening mechanisms of a 15Cr-ODS steel produced by mechanical alloying and Spark Plasma Sintering

Weijuan Li, Haijian Xu, Xiaochun Sha, Jingsong Meng, Zhaodong Wang2018

Surface error modeling, evaluation and optimization of large optics in inertial confinement fusion laser system

Wang Hui, Zhang Zheng, Liu Tianye, Liu Changchun, Yuan Xiaodong2018

Determination of hydrogen isotopes and isomers by different deactivated alumina PLOT columns

Weiwei Wang, Xingbi Ren, Lidong Xia, Hairong Li, Shuming Peng2018

Neutronic design optimization of ITER TBM port#2 bio-shield plug

H.L. Swami, Sanchit Sharma, A.K. Shaw, C. Danani

2018

An online method to measure tritium production rate of fusion-fission hybrid reactor in CAEP

Tie He, Xinhua Wang, Li An, Jian Yang, Pu Zheng2018

The mechanical properties of high entropy (-like) alloy Wx(TaTiVCr)1-x via first-principles calculations

Xiao-Jing Yao, Xue-Feng Shi, Ya-Ping Wang, Guo-Yong Gan, Bi-Yu Tang2018

Fatigue and fracture analysis on EAST divertor monoblock heat sink in H-mode operation

Kun Lu, Peng Liu, Xinyuan Qian, Xin Mao, Yuntao Song2018

Effects of interstitial atoms (N/O) in bcc Fe from first-principle calculations

Z. Lv, J. Fan, K. Guan, Z. Wu, W. Fu2018

Experimental investigation on deuterium effects on the tensile performance of two types of China Reduced Activation Ferritic-Martensitic steels

Zhanlei Wang, Kaigui Zhu, Xin Xiang, Lei Zhang, Chang An Chen2018

Experimental study on single-phase frictional pressure drop for water flow under high heat fluxes

Pengcheng Guo, Junhui Wang, Jianguo Yan, Xingqi Luo, Qincheng Bi2018

Estimation of neutron yields produced from SS316L, CuCrZr, and graphite targets for MeV-energy electrons toward JT-60 Tokamak fusion device

Atsuhiko M. Sukegawa, Koichi Okuno, Seiichiro Tanaka2018

Application of laser induced breakdown spectroscopy for fast depth profiling analysis of type 316 stainless steel parts corroded by liquid lithium

Chuan Ke, Ying Li, Xiang Liu, Fujun Gou, Yong Zhao2018

Analysis liquid lithium corrosion resistance of Er2O3 coating revealed by LIBS technique

Ying Li, Chuan Ke, Xiang Liu, Fujun Gou, Yong Zhao2018

Solutions to fix the shine-through at the hypervapotrons of SPIDER beam dump

M. Zaupa, J. Chareyre, S. Dal Bello, M. Dalla Palma, P. Zaccaria2018

Exploiting information of fusion component tests for failure rate estimation: Divertor Inner Vertical Target component study case

Danilo Nicola Dongiovanni, Tomas Iesmantas, Pierre Gavila, Tonio Pinna2018

Heat loading behavior and thermomechanical analyses on plasma spray tungsten coated reduced-activation ferritic/martensitic steel

K. Tokunaga, T. Hotta, K. Araki, A. Kurumada, K. Nakamura2018

Thermo-mechanical stress analysis of the water cooled DEMO First Wall mock-up components

Robin Kamenický, Phani Kumar Domalapally, Xavier Arnoult2018

Design features and commissioning of pulse arc plasma source and power supply system for the VEST neutral beam injection system

Bong-Ki Jung, Tae-Seong Kim, Sun-Ho Kim, Seung-Ho Jeong, Kwang-Won Lee2018

Detailed design of the RFX-mod2 machine load assembly

Simone Peruzzo, Marco Bernardi, Roberto Cavazzana, Samuele Dal Bello, Lauro Trevisan2018

Progress in the design of the superconducting magnets for the EU DEMO

V. Corato, T. Bagni, M.E. Biancolini, R. Bonifetto, R. Zanino2018

Manufacturing and testing of ITER-like divertor plasma facing mock-ups for DEMO

Eliseo Visca, B. Böswirth, E. Cacciotti, V. Cerri, F. Maviglia2018

Computational thermofluid-dynamic analysis of DEMO divertor cassette body cooling circuit

P.A. Di Maio, S. Garitta, J.H. You, G. Mazzone, E. Vallone2018

Corrosion–erosion and mass transfer dynamic behaviors of reduced activation ferritic/martensitic steel in a nonisothermal Pb-17Li system

Masatoshi Kondo, Yoshimitsu Hishinuma, Takayoshi Norimatsu, Takeo Muroga2018

Evaluation of tritium leakage rate into seawater in fusion DEMO cooling water system

Yuya Miyoshi, Akira Aoki, Ryoji Hiwatari, Yoshiteru Sakamoto, Kenji Tobita2018

DEMO design using the SYCOMORE system code: Influence of technological constraints on the reactor performances

C. Reux, S. Kahn, L. Zani, B. Pégourié, P. Sardain2018

Preliminary design of EU DEMO helium-cooled breeding blanket primary heat transfer system

I. Moscato, L. Barucca, S. Ciattaglia, P.A. Di Maio, G. Federici2018

Status of EU DEMO heat transport and power conversion systems

L. Barucca, S. Ciattaglia, M. Chantant, A. Del Nevo, I. Moscato2018

Status of water cooled ceramic breeder blanket development

Yoshinori Kawamura, Hisashi Tanigawa, Takanori Hirose, Hyoseong Gwon, Toshihiko Yamanishi2018

前へ 1...153 154 155 156 157 158 159...505 次へ