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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
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Modelling of plasma gamma ray sources in large tokamaks

Andrej Žohar, Igor Lengar, Massimo Nocente, Luka Snoj, Žiga Štancar2021

Computational investigation on the explosively actuated switch utilized in quenching protection system

Cunwen Tang, Zhiquan Song, Chuan Li, Zijian Wang, Peng Fu2021

Specific features of eddy current analysis with ANSYS® for fast plasma current decay event in W7-X

J. Zhu, V. Bykov, I. Pagani, F. Lucca, H-S. Bosch2021

Neutral beam injection for DEMO alternative scenarios

P. Vincenzi, J.-F. Artaud, E. Fable, G. Giruzzi, H. Zohm2021

Cold Performance Tests of the ITER 68 kA HTS Current Lead Prototypes

Q. Du, C. Liu, K. Ding, K. Lu, P. Bauer2021

Nonlinear model predictive control (NMPC) based trajectory tracking on EAST Articulated Maintenance Arm (EAMA)

Xuanchen Zhang, Haifeng Yao, Qiong Zhang, Zhiwei Hao, Yuntao Song
2021

Study of breakdown and plasma formation in the KTM tokamak with the massive conductive vacuum chamber

B. Chektybayev, A. Sadykov, E. Batyrbekov, M. Skakov, V. Pavlov2021

Selective electromagnetic induction heating of metal particles in molten salt for tritium extraction: A systematic numerical investigation

Katsuaki Tanabe2021

CAKE: Consistent Automatic Kinetic Equilibrium reconstruction

Z.A. Xing, D. Eldon, A.O. Nelson, M.A. Roelofs, E. Kolemen2021

Numerical simulation of liquid metal MHD flows in a conducting rectangular duct with triangular strips

Lang Yang, Jie Mao, Baolong Xiong2021

Effect of temperature on the growth and surface bursting of He nano-bubbles in W under fusion-relevant He ion irradiations

Chunjie Niu, Yang Zhang, Yunqiu Cui, Xiaoping Li, Dongping Liu2021

Effect of the LEHs film transmissivity on spherical hohlraum cryogenic target after the shield is removed

Peng Tang, Qilong Liao, Yunya Dai, Xiaoyuru Chen2021

Neutronic analyses of port impact on blankets and superconducting coils of CFETR

Wei Shi, Wei Li, Qin Zeng, Hongli Chen2021

Identification of precipitate phases in CLAM steel

Yinzhong Shen, Xiaoling Zhou, Xi Huang, Zhijun Fan, Xingjian Shi2021

Tomographic reconstruction of emissive profile in the divertor region for the visible light imaging diagnostic on Experimental Advanced Superconducting Tokamak

Zhiyuan Lu, Shifeng Mao, Jianhua Yang, Tingfeng Ming, Minyou Ye2021

Effects of bed dimension, friction coefficient and pebble size distribution on the packing structures of the pebble bed for solid tritium breeder blanket

Yongjin Feng, Baoping Gong, Hao Cheng, Xiaofang Luo, Xiaoyu Wang2021

Numerical simulations with RELAP5-3D of the first experimental campaign on In-box LOCA transient for HCLL TBS

A. Venturini, M. Utili, N. Forgione2021

Numerical simulations of radioactive dust particle releases during a Loss Of Vacuum Accident in a nuclear fusion reactor

Riccardo Rossi, Pasqualino Gaudio, Luca Martellucci, Andrea Malizia2021

Characterization of the soft zone in dissimilar welds joint of 2.25Cr-1Mo and lean duplex LDX2101 steel

C. Pandey, J.G. Thakare, P.K. Taraphdar, P. Kumar, S. Sirohi2021

An adaptive optimization reverse regulation method for neutron spectrum based on standardized response module

Chenglong Cao, Quan Gan2021

Design and characteristics of a modular integrated power supply for the system of flashlamp-pumped in inertial confinement fusion

Bin Yu, Yuan Pan, Lee Li, Jiaming Xiong, Haibo Wu2021

Performance of the first neutral beam injector at the Wendelstein 7-X stellarator

Annabelle Spanier, Dirk Hartmann, Simppa Äkäslompolo, Oliver Ford, Robert C. Wolf2021

RF discharge mirror cleaning for ITER optical diagnostics using 60 MHz very high frequency

L. Marot, L. Moser, R. Steiner, W. Erni, E. Meyer2021

Key manufacturing technologies of the CFETR 1/8 vacuum vessel sector mockup

Jianguo Ma, Jiefeng Wu, Zhihong Liu, Rui Wang, Haibiao Ji2021

Accelerated version of NUBEAM capabilities in DIII-D using neural networks

Shira M. Morosohk, Mark D. Boyer, Eugenio Schuster2021

Effect of ITER CS and PF magnets on EM loads outside vacuum vessel at plasma disruption events

D.N. Arslanova, A.V. Belov, E.I. Gapionok, V.P. Kukhtin, S.E. Sytchevsky2021

Assessment of SIMMER-III code in predicting Water Cooled Lithium Lead Breeding Blanket “in-box-Loss of Coolant Accident”

Marica Eboli, Nicola Forgione, Alessandro Del Nevo2021

A neutronics probe ball method on tritium generation rate simulation for a nuclear fusion reactor blanket

Yang Qiu, Changle Liu2021

Flush-mounted Langmuir probes in the WEST tokamak divertor

R. Dejarnac, D. Sestak, J.P. Gunn, M. Firdaouss, H. Roche2021

Manufacturing design of typical attachments in the vacuum vessel of ITER

Yugyeong Kim, Mikhail Privalov, Juntao Jing, Arnaud Mestric2021
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