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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

Cylindrical breeding blankets for fusion reactors

Hisashi Tanigawa, Hyoseong Gwon, Takanori Hirose, Yoshinori Kawamura, Yasushi Oda2018

Plasma exhaust and divertor studies in Japan and Europe broader approach, DEMO design activity

Nobuyuki Asakura, Kazuo Hoshino, Hiroyasu Utoh, Youji Someya, Noriyasu Ohno2018

Design constraints on new vacuum components of RFX-mod2 upgrade using electrical modeling of reversed field pinch plasma

Roberto Cavazzana, Laura Marsango, Simone Peruzzo, Matteo Zuin, Emilio Martines2018

RAMI: The main challenge of fusion nuclear technologies

David Maisonnier2018

Comparison of shear strength and failure mechanisms of lap joint between REBCO tapes bonded by different joining techniques

Luis Ernesto Aparicio, Satoshi Ito, Hidetoshi Hashizume2018

Design of remote handling, nuclear and vacuum compatible connectors for mineral insulated thermocouples of ITER neutral beam injectors

Mauro Dalla Palma, Nicola Pomaro, Etienne Delmas, Lennart Svensson, Roberto Pasqualotto2018

Hydraulic modeling of a segment of the EU DEMO HCPB breeding blanket back supporting structure

Andrea Bertinetti, Antonio Froio, Bradut-Eugen Ghidersa, Francisco Alberto Hernández González, Roberto Zanino2018

Numerical assessment of the thermomechanical behaviour of the DEMO Water-Cooled Lithium Lead inboard blanket equatorial module

P.A. Di Maio, P. Arena, G. Bongiovì, P. Chiovaro, R. Forte2018

EU DEMO EC system preliminary conceptual design

Saul Garavaglia, Gaetano Aiello, Stefano Alberti, Konstantinos Avramidis, Minh Quang Tran2018

Assessment of activated corrosion products for the DEMO WCLL

Luigi Di Pace, Lina Quintieri2018

Deuterium retention in neutron-irradiated single-crystal tungsten

M. Shimada, Y. Oya, W.R. Wampler, Y. Yamauchi, Y. Hatano2018

Breeding blanket system design implications on tritium transport and permeation with high tritium ion implantation: A MATLAB/Simulink, COMSOL integrated dynamic tritium transport model for HCCR TBS

Alice Ying, Hongjie Zhang, Brad Merrill, Mu-Young Ahn, Seungyon Cho2018

Design and analysis of a new configuration of secondary circuit of the EU-DEMO fusion power plant using GateCycle

Leszek Malinowski, Monika Lewandowska, Fabio Giannetti2018

Tritium supply and use: a key issue for the development of nuclear fusion energy

Richard J. Pearson, Armando B. Antoniazzi, William J. Nuttall2018

Effect of neutral leaks on pumping efficiency in 3D DEMO divertor configuration

Stylianos Varoutis, Yuri Igitkhanov, Christian Day, Holger Strobel, Ronald Wenninger2018

Pre-conceptual design of DEMO upper port duct bellows

Oriol Costa Garrido, Boštjan Končar, Richard Brown, Christian Bachmann2018

Tokamak systems analyses using a fast 1D transport solver: Models and assessments

Jose Carlos Rivas, Emiliano Fable, Richard Kemp, Hanni Lux, Ronald Wenninger2018

Overview of the ITER remote maintenance design and of the development activities in Europe

C. Damiani, J. Palmer, N. Takeda, C. Annino, M. Saito2018

Assessment of mixed neutron and photon radiation ratios using a tissue equivalent proportional counter on KSTAR

Y.S. Lee, U.W. Nam, J.G. Kwak, H.S. Kim, S.H. Kim2018

Recent accomplishments of the fusion safety program at the Idaho National Laboratory

Brad J. Merrill, Lee C. Cadwallader, Masashi Shimada, Paul W. Humrickhouse, Robert J. Pawelko2018

CFD-based shape optimization on cross-section of monoblock fusion divertor cooling channel for minimizing local heat flux

Do Kyun Lim, Youngjae Park, Hyungdae Kim, Eung Soo Kim2018

Characteristic research of pellet injection system in KSTAR

SooHwan Park, HongTack Kim, JaeIn Song, InSik Woo, YeongKook Oh2018

Modelling of the neutron production in a mixed beam DT neutron generator

Aljaž Čufar, Paola Batistoni, Zamir Ghani, Luca Giacomelli, Luka Snoj2018

Development of the safety code AINA for the European DEMO designs

Eduard Baeza, Alfredo de Blas, Albert Riego, Marco Fabbri2018

Investigation of beryllium pebbles produced by powder metallurgy for HCPB breeding blanket

I.B. Kupriyanov, G.N. Nikolaev, S.K. Zavjalov, L.A. Kurbatova, V.P. Chakin2018

Effects of test environment on high temperature fatigue properties of reduced activation ferritic/martensitic steel, F82H

Takanori Hirose, Hideo Sakasegawa, Motoki Nakajima, Taichiro Kato, Hiroyasu Tanigawa2018

Technical innovations for ITER Edge Thomson scattering measurement system

Eiichi Yatsuka, Michele Bassan, Takaki Hatae, Tsuyoshi Yamamoto, Kiyoshi Itami2018

A preliminary assessment of the vacuum performance in the beamline during IFMIF-DONES operation

V. Hauer, Chr. Day2018

Status of the final design of the EC UPP launcher

Peter Spaeh, Gaetano Aiello, René Chavan, Mario Gagliardi, Bastian Weinhorst2018

Cracks avoidance with a modified solid tungsten divertor in ASDEX Upgrade

I. Zammuto, M. Li, A. Herrmann, N. Jaksic, A. Kallenbach2018
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