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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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Impact Factor

1.7

Citescore

3.7

最新論文

  • Planar coil design for the Helios stellarator fusion power plant
  • Equilibrium optimization of the Helios planar coil stellarator power plant
  • Core profile prediction and transport analysis of the Helios stellarator fusion power plant
  • Superconducting planar coils for magnetic field shaping in the Helios Stellarator
  • Design of the superconducting encircling coils for Helios, the planar coil stellarator
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全 15,241 件の論文
並び順:新しい順古い順被引用数順

The roles of fuzzy W surfaces in avoiding W cracking during ELMs-like heat loads

Weifeng Liu, Xu Zhao, Chunjie Niu, Kefeng Shang, Dongping Liu2025

Faraday shield dissipation in the drivers of SPIDER based on electromagnetic 3D calculations

D. López-Bruna, S. Denizeau, I. Predebon, A. La Rosa, P. Agostinetti2025

Design and development of divertor pipe welding tool for fusion reactor

Lei Zheng, Wanjin Zhang, Yongjun Sun, Yu Zhang, Tao Wang2025

Adhesion properties and damage tolerance of W-Fe graded interfaces from first-principles calculation

Liang Chen, Qian Wang, Chaoping Liang2025

Design of 1D carbon fiber composite tiles infrared diagnostic calorimeter for the CRAFT NNBI test platform

Yue Hu, Yongjian Xu, Tao Yang, Yahong Xie, Lizhen Liang2025

Hydraulic analysis of the DTT divertor module

Davide Caprini, Morena Angelucci, Emanuela Martelli, Fabio Crescenzi, Selanna Roccella
2025

Development of liquid spray neutralizer for neutral beam injection (NBI) for fusion devices

Sargis Ter-Avetisyan2025

Compensating control delays in the CFETR Multi-Purpose Overload Robot for divertor maintenance by using transformer-enhanced Temporal Convolutional Network

Chenhui Wan, Zibo Qi, Hongbin Huang, Jie Liu, Zhongxu Hu2025

Initial plasma achieved within engineering constraints in the PLATO tokamak

T. Nishizawa, Y. Nagashima, C. Moon, D. Nishimura, A. Fujisawa2025

A multi-degree-of-freedom water hydraulic manipulator in nuclear applications: Design and experiments

Weidi Huang, Zhiwen Pan, Changhong Guo, Min Cheng, Bing Xu2025

Feasibility study of the high-power millimeter-wave collective Thomson scattering diagnostic system on HL-3 tokamak

Feng Zhang, Mei Huang, Gangyu Chen, Wanxin Zheng, He Wang2025

Fast visible imaging diagnostic for inductively driven pellet injector in Aditya-U Tokamak

Devilal Kumawat, Kumudni Tahiliani, SK Pathak, Joydeep Ghosh, S. Chaturvedi2025

Novel modular and Git-based approach for the management and development of radiation transport models

A. Cubi, M. Fabbri, M. Cavinato, A. Jokinen, A. Portone2025

Analyzing the safety framework for fusion demonstration plants in Korea

Hyun Soo Tho, Jae Young Choi, Sung Bo Moon, Nam Il Her, Jeung Han Lee2025

Study of runaway electrons during EAST plasma start-up

Y. Hong, L. Zeng, T. Tang, D.L. Chen, X. Gao2025

Editorial Board

2025

Validation of FE analysis results with selected W7-X in-vessel temperature measurements

M. Khokhlov, A. Lorenz, V. Smolik, V. Bykov, Y. Gao2025

Irradiation hardening and mechanical behavior of K-RAFM steels subjected to Fe ion irradiation at doses up to 20 dpa

Sangeun Kim, Jinwoo Park, Mingyu Lee, Taeyun Kwon, Chansun Shin2025

Remote maintenance strategy of the volumetric neutron source shielding blanket

Rocco Mozzillo, Vincenzo Claps, Nicolas Calzone, Günter Janeschitz, Christian Bachmann2025

The management and cascading of geometrical requirements from designer to manufacturer in the ITER life cycle

Gabriele D’Amico, Francisco Javier Fuentes, Andres Jimenez, Francesca Giovanna Lanzotti, Gianluca Picci2025

Modeling of hydrogen isotope permeation through liquid Sn supported by various metal substrates

Yuya Ando, Ryo Hatano, Ryosuke Ohata, Teppei Otsuka2025

Feasibility study of the DEMO divertor target baffles

F. Crescenzi, M. Cerocchi, R. De Luca, F. Giorgetti, J.H. You2025

Automated design rationalization of robot component geometry for ITER blanket remote handling system

Takuya Iwamoto, Yuto Noguchi, Nobukazu Takeda2025

ITER core plasma thomson scattering diagnostic collection optics design

M. Amarika, G. Beaskoetxea, A. Estevez, M. Roldán, J. Puig2025

Status of the radiofrequency modelling of the WEST Ion Cyclotron Travelling Wave Array launcher

Riccardo Ragona, Vincent Maquet, Julien Hillairet2025

Diffusion bonding between tungsten base tiles and copper for fusion applications

F. Giorgetti, P. Lorusso, M. Cerocchi, F. Crea, J.H. You2025

An actively cooled mock-up with massive tungsten assembled to Eurofer97 tested up to 3 MW/m²

M. Richou, M. Ramaniraka, G. Peyron, H. Roche, E. Meillot2025

Chemical compatibility of zircaloy-4 in heavy liquid metals LiPb, PbBi and Sn

Sota Hagiwara, Masatoshi Kondo, Yota Koike, Minho Oh, Kan Sakamoto2025

Activity assessment in water coolant loops and rooms using the SAETTA tritium transport code

Federico Hattab, Vincenzo Narcisi, Cristiano Ciurluini, Fabio Giannetti, Alessia Santucci2025

Progress in the development of radiation detectors for fusion neutron source A-FNS

Kunihiro Ogawa, Longyong Liao, Takashi Kobuchi, Saori Kurita, Isao Murata2025
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