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
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
全 15,142 件の論文
並び順:新しい順古い順被引用数順

Heat management for water-hydraulic systems at ITER remote handling

J. Väyrynen, L. Aha, J. Mattila, S. Esqué, R. Sharratt2019

Neural network based prediction of heat flux profiles on STRIKE

Rita S. Delogu, Augusto Montisci, Antonio Pimazzoni, Gianluigi Serianni, Giuliana Sias2019

Strategy and methods on thermal integrity management of the ITER Thermal Shield

Germán Pérez-Pichel, Térénig Arzoumanian, Chang Hyun Noh, Manoj Panchal, Chang Ho Choi2019

Conceptual studies on spectroscopy and radiation diagnostic systems for plasma control on DEMO

W. Gonzalez, W. Biel, Ph. Mertens, M. Tokar, Ch. Linsmeier2019

The development of technology of Be/CuCrZr joining using induction brazing

A. Gervash, R. Giniyatulin, T. Guryeva, D. Glazunov, O. Sevryukov2019

Numerical investigation of mechanical and thermal characteristics of binary-sized pebble beds using discrete element method

Youngmin Lee, Suhwan Yu, Mu-Young Ahn, Yi-Hyun Park, Dongwoo Sohn2019

Engineering and integration risks arising from advanced magnetic divertor configurations

R. Kembleton, G. Federici, R. Ambrosino, F. Maviglia, M. Suiko2019

Upgraded concepts and design of an in vessel inspection system for fusion reactors

Carlo Neri, Mario Ferri De Collibus, Paolo Rossi, Giampiero Mugnaini, Marcello Nuvoli2019

Development of tungsten armored high heat flux plasma facing components for ITER like divertor application

K. Premjit Singh, S.S. Khirwadkar, Nikunj Patel, Prakash Mokaria, Kalpesh Galodiya2019

Methodology for reverse engineering analysis of ITER as-built integrated systems

F. Javier Fuentes, Jean-Jacques Cordier, Pierric Leonard, Lucas Scherrer, Tudorel Popa2019

Software quality management approach for WEST CODAC

J. Colnel, S. Bremond, G. Caulier, P. Moreau, B. Santraine2019

First considerations on the Balance of Plant for a HELIAS fusion power plant

Felix Warmer, Evaldas Bubelis2019

The relationship between structural changes of ceramic coatings and γ-ray irradiation effect on deuterium permeation

Hikari Fujita, Takumi Chikada, Jan Engels, Jumpei Mochizuki, Takayuki Terai2019

Optimal pump regeneration model for fuel cycle of ITER

Suh-Young Lee, Min Ho Chang, Jae-Uk Lee, Sei-Hun Yun, Euy Soo Lee2019

On the effect of stiffening plates configuration on the DEMO Water Cooled Lithium Lead Breeding Blanket module thermo-mechanical behaviour

P.A. Di Maio, P. Arena, G. Bongiovì, I. Catanzaro, R. Forte2019

Recent achievements of the Pd-Ag membrane technologies in tritium extraction system applications

Alessia Santucci, Rodrigo Antunes, Giacomo Bruni, Federica Mallozzi, Mirko Sansovini2019

Acceleration grid power supply conversion system of the MITICA neutral beam injector: On site integration activities and tests

L. Zanotto, M. Dan, V. Toigo, F. Ferrari, C. Panizza2019

The strategy toward realization of the helical fusion reactor FFHR-c1

Junichi Miyazawa, Takuya Goto, Hitoshi Tamura, Teruya Tanaka, Akio Sagara2019

Mechanical properties and microstructure characterization of Eurofer97 steel variants in EUROfusion program

Xiang Chen, Arunodaya Bhattacharya, Mikhail A. Sokolov, Logan N. Clowers, Michael Rieth2019

Thermal-hydraulic analysis for first wall and thermal shield of Divertor Tokamak test facility

Fabio Maviglia, Riccardo De Luca, Selanna Roccella, Giorgio Maddaluno, Eliseo Visca2019

First thermal-hydraulic analysis of a CO2 cooled pebble bed blanket for the EU DEMO

Shuai Wang, Francisco A. Hernández, Guangming Zhou, Hongli Chen2019

Mechanical design of the JT-60SA cryogenic pipe system

Kyohei Natsume, Koji Kamiya, Kazuma Fukui, Katsumi Kawano, Takaaki Isono2019

Fracture mechanics assessment of divertor vertical target under thermal loading conditions

Jae Min Sim, Sang Yun Je, Ji-Hoon Kang, Yoon-Suk Chang2019

Prebaking of T-15MD vacuum vessel

A.P. Khvostenko, I.O. Anashkin, E.N. Bondarchuk, K.V. Borisenko, V.I. Tanchuk2019

Evaporation and condensation model for a cooling system of the LiPb cold trap device

Tomas Romsy, Pavel Zacha2019

ST40 data and control

O. Asunta, P.F. Buxton, J.B. Lister, E. Pinkney, L. Scott2019

How fusion power can contribute to a fully decarbonized European power mix after 2050

C. Bustreo, U. Giuliani, D. Maggio, G. Zollino2019

EU DEMO safety and balance of plant design and operating requirements. Issues and possible solutions

S. Ciattaglia, G. Federici, L. Barucca, R. Stieglitz, N. Taylor2019

Preliminary configuration of the torus vacuum pumping system installed in the DEMO lower port

T. Giegerich, C. Day, C. Gliss, X. Luo, S. Jimenez2019

MEST: A new Magnetic Energy Storage and Transfer system for improving the power handling in fusion experiments

Roberto Piovan, Elena Gaio, Francesco Lunardon, Alberto Maistrello2019
前へ1...128129130131132133134...505次へ