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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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Development of lower manipulator system for breeding blanket maintenance within large port-based tokamaks

Marcell Málics, László Poszovecz, Aditya Sinha, Ian Chiang, Imre Katona2024

Blanket test facility for mockup testing on water cooled ceramic breeder blanket system

Takuya Katagiri, Wenhai Guan, Atsushi Wakasa, Motoki Nakajima, Hiroyasu Tanigawa2024

Deuterium enrichment by proton exchange membrane water electrolysis with electrolyte circulation

Ibuki Sato, Koichiro Furusawa, Mikito Ueda, Hisayoshi Matsushima2024

Reducing the user burden when running MELCOR for accident analysis for a tokamak

G. Karajgikar, J.J. Nebrensky2024

Construction of GVR weight windows maps from very low density transport simulations

Gonzalo Farga-Niñoles, Francisco Ogando, Javier Alguacil, Patrick Sauvan2024

Thermal and structural analysis of the DONES target system under steady state and transient loading conditions

I. Catanzaro, P. Arena, D. Bernardi, G. Bongiovì, E. Vallone2024

Deuterium permeation of low-activation vanadium alloys possible for reuse in a short time in fusion reactors

Aoi Yoshizawa, Yuji Yamauchi, Takuya Nagasaka, Satoshi Tomioka, Naoki Higashi2024

Study on hot isostatic pressing conditions of ARAA for fabrication of the breeding blanket first wall

Hyoseong Gwon, Yunsong Jung, Yi-Hyun Park, Jae-Sung Yoon, Seungyon Cho2024

Assessment of different lifting devices for the shipping bays for DONES main building

Yan Wang, Martin Mittwollen2024

Neural network-based source biasing to speed-up challenging MCNP simulations

E. Martínez-Fernández, J. Alguacil, J. Sanz, R. Juárez2024

Progress and challenges of the ECH transmission line design for DTT

A. Moro, A. Bruschi, F. Fanale, P. Fanelli, E. Vassallo2024

Material flow planning in fusion test facilities

Timo Lehmann, Georg Fischer, Felix Rauscher, Sebastian Köhler, Fernando Arranz2024

A review of pipe cutting, welding, and NDE technologies for use in fusion devices

Yao Ren, Robert Skilton2024

Development of real-time density feedback control on MAST-U in L-mode

G.L. Derks, B. Kool, C. Vincent, S. Elmore, M. van Berkel2024

Development of potassium doped tungsten plate for fusion reactor applications

Shuhei Nogami, Naoya Matsuta, Kei Miura, Kenta Okutani, Tomohiro Takida2024

First-principles study of the energetics of Fe interstitial clusters in vanadium

Xing Wang, Pengbo Zhang, Guofeng Li, Mingliang Wei, Yichao Wang2024

Re-evaluation of shielding ability and induced activity of KSTAR with increased neutron yields

UkJae Lee, Nam-Suk Jung, Hee-Seock Lee, Hee-Soo Kim2024

Overview of European efforts and advances in Stellarator power plant studies

Felix Warmer, J. Alguacil, D. Biek, T. Bogaarts, F.R. Urgorri2024

Free boundary equilibrium determination of HL-3 discharges

Y.Y. Zhong, L. Xue, W.L. Zhong, J.X. Li, H. Heumann2024

Development of a real-time digital pulse acquisition and processing algorithm for compact neutron spectrometer on EAST

Yong-Qiang Zhang, Li-Qun Hu, Wei Lu, Guo-Qiang Zhong, Qiang Li2024

Key technologies of manufacturing and testing for the ITER blanket shield block

Sa-Woong Kim, Si-Kun Chung, Jun-Sung Chang, Duck-Hoi Kim, Ki-Jung Jung2024

Damage assessment of the Faraday Shield in the RF driver of the negative ion source test stand SPIDER

Alessandro La Rosa, Giovanni Berton, Sylvestre Denizeau, Mauro Pavei, Valentina Zin2024

Tritium breeding ratio optimization in simple multi-layer blanket with genetic algorithm

Soobin Lim, Kyoung-Jae Chung, Y.S. Hwang2024

In-vessel inspection system: Development and testing activities of high vacuum and temperature technologies for fusion remote handling

ManoahStephen M, Naveen Rastogi, Ravi Ranjan Kumar, Krishan Kumar Gotewal, Siju Geroge2024

Induction brazing of DEMO's large bore cooling pipes

Jenő Kádi, Miklós Palánkai, Márton Gregor, József Szőke, Tristan Tremethick2024

Eddy current actuated fast valve development for disruption mitigation applications

D. Nagy, D.I. Réfy2024

Analysis of transport-activation internal coupling method implemented in Monte Carlo code cosRMC

Shengzhe Wang, Shichang Liu, Jun Wu, Yixue Chen2024

Conceptual design of DEMO breeding blanket in-vessel toroidal transporter

Vincenzo Claps, Christian Bachmann, Günter Janeschitz, Rocco Mozzillo, Thomas Steinbacher2024

Image inpainting for ECEI based on DeepFillv2 model

Zijian Xuan, Zhoujun Yang, Chi Lei, Zezhi Yu, Yonghua Ding2024

Characterisation of the neutron field for streaming analyses in TT operations at JET

Igor Lengar, Theodora Vasilopoulou, Mariusz Kłosowski, Rosaria Villari, Luka Snoj2024

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