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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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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

Structural analysis of ITER multi-purpose deployer

Manoah Stephen Manuelraj, Pramit Dutta, Krishan Kumar Gotewal, Naveen Rastogi, Chang-Hwan Choi2016

Impact hammer test of ITER blanket remote handling system

Yuto Noguchi, Takahito Maruyama, Kenichi Ueno, Masafumi Komai, Satoshi Kakudate2016

Re-evaluation of SiC permeation coefficients at high temperatures

Yasushi Yamamoto, Yuichiro Murakami, Hirosato Yamaguchi, Takehiro Yamamoto, Satoshi Konishi2016

Thermomechanical characterization of joints for blanket and divertor application processed by electrochemical plating

Wolfgang Krauss, Julia Lorenz, Jürgen Konys, Widodo Basuki, Jarir Aktaa2016

Recent technical progress on BA Program: DEMO activities and IFMIF/EVEDA

T. Yamanishi, N. Asakura, K. Tobita, S. Ohira, N. Nakajima2016

Performance optimization of internal tin process multifilamentary Nb3Sn strands

Ke Zhang, Pingxiang Zhang, Yigong Shi, Jianwei Liu, Yong Feng2016

Circumferential tensile test method for mechanical property evaluation of SiC/SiC tube

Ju-Hyeon Yu, Hirotatsu Kishimoto, Joon-soo Park, Naofumi Nakazato, Akira Kohyama2016

Progress of ITER full tungsten divertor technology qualification in Japan: Manufacturing full-scale plasma-facing unit prototypes

Koichiro Ezato, Satoshi Suzuki, Yohji Seki, Hirokazu Yamada, Takeshi Hirai2016

Structural integrity for DEMO: An opportunity to close the gap from materials science to engineering needs

M. Porton, B.P. Wynne, R. Bamber, C.D. Hardie, M. Kalsey2016

HELOKA-HP thermal-hydraulic model validation and calibration

Xue Zhou Jin, Bradut-Eugen Ghidersa, Aurelian Florin Badea2016

Simulation of surface cracks measurement in first walls by laser spot array thermography

Cuixiang Pei, Jinxin Qiu, Haocheng Liu, Zhenmao Chen2016

ITER ECRH Upper Launcher: Test plan for qualification of the Diamond Torus Window Prototype III

Sabine Schreck, Gaetano Aiello, Andreas Meier, Dirk Strauss, Theo Scherer2016

Hydrogen incorporation into tungsten deposits growing by hydrogen plasma sputtering

Kazunari Katayama, Mizuki Noguchi, Hiroyuki Date, Satoshi Fukada2016

Cross-section sensitivity and uncertainty analysis of the FNG copper benchmark experiment

I. Kodeli, K. Kondo, R.L. Perel, U. Fischer2016

Busbar arcs at large fusion magnets: Model experiments on busbar arcing in a double-walled feeder tube with the LONGARC device

Dmitry Klimenko, Volker Pasler2016

Neutronic study of extended DONES irradiation module

Fernando Mota, Joaquín Molla2016

Neutronic analyses of design issues affecting the tritium breeding performance in different DEMO blanket concepts

Pavel Pereslavtsev, Christian Bachmann, Ulrich Fischer2016

Objectives and status of EUROfusion DEMO blanket studies

L.V. Boccaccini, G. Aiello, J. Aubert, C. Bachmann, L. Vala2016

Study on thermal mixing of liquid–metal free-surface flow by obstacles installed at the bottom of a channel

Koji Kusumi, Tomoaki Kunugi, Takehiko Yokomine, Zensaku Kawara, Erik Gilson2016

Effects of trapped energetic ions on the interchange mode

Seiya Nishimura, Timothee Nicolas, Xiaodi Du2016

Vibration of fusion reactor components with magnetic damping

Gabriele D’Amico, Alfredo Portone, Guglielmo Rubinacci, Pietro Testoni2016

Tritium desorption and tritium removal from tungsten pre-irradiated with helium

Yuji Nobuta, Yuji Hatano, Yuji Torikai, Masao Matsuyama, Yuji Yamauchi2016

Fabrication of short SiC fiber reinforced SiC matrix composites with high fiber volume fraction

Joon-Soo Park, Hiroshi Nishimura, Daisuke Hayasaka, Ju-Hyeon Yu, Akira Kohyama2016

Pipe stress analysis on HCCR-TBS ancillary systems in conceptual design

Mu-Young Ahn, Seungyon Cho, Eo Hwak Lee, Yi-Hyun Park, Youngmin Lee2016

Analysis of the ITER computational shielding benchmark with the Monte Carlo TRIPOLI-4® neutron gamma coupled calculations

Yi-Kang Lee2016

On the EU approach for DEMO architecture exploration and dealing with uncertainties

M. Coleman, F. Maviglia, C. Bachmann, J. Anthony, R. Wenninger2016

Final design of ITER port plug test facility

Thierry Cerisier, Bruno Levesy, Alexander Romannikov, Yuri Rumyantsev, Ekaterina Mironova2016

A study of plasma facing tungsten components with electrical discharge machined surface exposed to cyclic thermal loads

Yohji Seki, Koichiro Ezato, Satoshi Suzuki, Kenji Yokoyama, Tomoyuki Hirayama2016

A new blanket tritium recovery experiment with intense DT neutron source at JAEA/FNS

Kentaro Ochiai, Yuki Edao, Tsuyoshi Hoshino, Yoshinori Kawamura, Chikara Konno2016

MHD effects on turbulent dissipation process in channel flows with an imposed wall-normal magnetic field

Yoshinobu Yamamoto, Tomoaki Kunugi2016

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