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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

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1.7

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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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並び順:新しい順古い順被引用数順

Material strength standard of F82H for RCC-MRx

Hideo Sakasegawa, Hiroyasu Tanigawa, Takanori Hirose, Taichiro Kato, Takashi Nozawa2020

Approach in improving reliability of DEMO

Tonio Pinna, Danilo N. Dongiovanni2020

Advancements in the HELIAS 5-B breeding blanket structural analysis

G. Bongioví, A. Häußler, the W7-X team2020

Analysis of irradiation experiments with activated water radiation source at the JSI TRIGA Research Reactor

Andrej Žohar, Anže Pungerčič, Klemen Ambrožič, Vladimir Radulović, Luka Snoj2020

Analysis of the influence of the different impurity seeding on the burn-up fraction and plasma confinement in the EU DEMO reactor

Irena Ivanova-Stanik, Mattia Siccinio, Michal Poradziński, Roman Zagórski2020

Tritium release and retention in beryllium and titanium beryllide after neutron irradiation up to damage doses of 23-38 dpa

Vladimir Chakin, Rolf Rolli, Ramil Gaisin, Ursula Hoeppener-Kramar, Milan Zmitko

2020

Verification and Validation of the Geant4 Monte Carlo Code Toolkit for DEMO TBR Evaluations

Elena Nunnenmann, Ulrich Fischer, Arkady Serikov2020

Parametric study of the influence of double-walled tubes layout on the DEMO WCLL breeding blanket thermal performances

Ilenia Catanzaro, Pietro Arena, Alessandro Del Nevo, Pietro Alessandro Di Maio, Emanuela Martelli2020

Feasibility of Li4SiO4 pebbles by drip casting and preliminary characterization

Rosa Lo Frano, Eleonora Stefanelli, Monica Puccini2020

On the numerical assessment of the thermal-hydraulic operating map of the DEMO Divertor Plasma Facing Components cooling circuit

P.A. Di Maio, R. Burlon, M. Giardina, J.H. You, E. Vallone2020

Thermal and mechanical analyses of W7-X plasma facing components for operation phase 2

Zhongwei Wang, Jean Boscary, Felix Schauer, Wendelstein 7-X team2020

Microstructural stability of tungsten coated CFC plates aiming to metal Wall experiments at JT-60SA

Hirotatsu Kishimoto, Wataru Kondo, Naofumi Nakazato, Masakatsu Fukumoto2020

Industrial-scale manufacturing experience of titanium beryllide block for DEMO blanket application

Ramil Gaisin, Vladimir Chakin, Pavel Vladimirov, Francisco A. Hernández, Maxim Kolmakov2020

Laminated composites using potassium doped tungsten

Shuhei Nogami, Takefumi Hazama, Hiroyuki Noto, Takuya Nagasaka, Akira Hasegawa2020

Recent advances in tritium modeling and its implications on tritium management for outer fuel cycle

Alice Ying, Marco Riva, Mu-Young Ahn, Carlos Moreno, Ion Cristescu2020

Preliminary design of the top cap of DEMO Water-Cooled Lithium Lead breeding blanket segments

R. Forte, P. Arena, G. Bongiovì, I. Catanzaro, E. Vallone2020

Structural pre-conceptual design studies for an EU DEMO equatorial EC port plug and its port integration

Peter Spaeh, Christian Bachmann, René Chavan, Aljaz Cufar, Minh Quang Tran2020

Progress of the R&D programme to develop a metal foil pump for DEMO

Stefan Hanke, Christian Day, Thomas Giegerich, Juri Igitkhanov, Jens Hofmann2020

Improvement of power quality in EAST power supply system based on hybrid active filter

Xianshun Shen, Ge Gao, Yanan Wu, Jing Lu, Yunxiang Tian2020

Robust vision using retro reflective markers for remote handling in ITER

Laura Gonçalves Ribeiro, Olli J. Suominen, Sari Peltonen, Emilio Ruiz Morales, Atanas Gotchev2020

Influence of Thermal Aging on Metallurgical, Mechanical and Corrosion Performance of Electron Beam Welded 18mm Thick AISI 316

Arun Kumar, Beant Singh, Sandeep Singh Sandhu2020

Modeling and optimization of the neutral beam line for plasma heating and current drive for the DEMO-FNS fusion neutron source project

S.S. Ananyev, E.D. Dlougach, A.I. Krylov, A.A. Panasenkov, B.V. Kuteev2020

Bulk porous materials as an alternative to pebble beds in tritium breeding blankets

Yan Zhong, Liwei Lin, Hongzhi Yang, Hao Wang, Bo Liu2020

Design of an advanced cesium oven for the prototype negative ion source in the CFETR-NNBI system

Yangyang Liu, Xin Zhang, Yuhong Xu, Zilin Cui, Guangjiu Lei2020

JADE, a new software tool for nuclear fusion data libraries verification & validation

Davide Laghi, Marco Fabbri, Lorenzo Isolan, Raul Pampin, Andrej Trkov2020

Thermal dynamic analyses of the primary heat transfer system for the WCCB blanket of CFETR

Xiaoman Cheng, Xuebin Ma, Peng Lu, Wenjia Wang, Songlin Liu2020

Development of technology for fabrication of prototype ion extraction grid for fusion research

Mukti Ranjan Jana, P. Ramsankar2020

Strain life analysis of the first wall mock up under ITER-relevant heat flux conditions

J. Du, Th. Loewenhoff, G. Pintsuk, J. Linke, M. Wirtz2020

High power characterisation of the ECRH transmission lines and power deposition calculations in the TJ-II stellarator

J. Martínez-Fernández, Á. Cappa, M. Tereshchenko, A. Tolkachev, G. Catalán2020

Development of Y2O3 dispersion strengthened Cu alloy using Cu6Y and Cu2O addition through the MA-HIP process

Bing Ma, Yoshimistu Hishinuma, Hiroyuki Noto, Yusuke Shimada, Takeo Muroga2020

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