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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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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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並び順:新しい順古い順被引用数順

Construction and commissioning of a hydrogen cryogenic distillation system for tritium recovery at ICIT Rm. Valcea

George Ana, Ion Cristescu, Mirela Draghia, Ciprian Bucur, Gheorghe Pasca2016

Application of a model to investigate the effective thermal conductivity of randomly packed fusion pebble beds

Xiaoliang Wang, Jie Zheng, Hongli Chen2016

Mechanical properties of W–Ti alloys from first-principles calculations

Jiang D.Y., Ouyang C.Y., Liu S.Q.2016

Helical mirrors for active plasma flow suppression in linear magnetic traps

V.V. Postupaev, A.V. Sudnikov, A.D. Beklemishev, I.A. Ivanov2016

Design and implementation of visual inspection system handed in tokamak flexible in-vessel robot

Hesheng Wang, Lifei Xu, Weidong Chen2016

Tritium fuel cycle modeling and tritium breeding analysis for CFETR

Hongli Chen, Lei Pan, Zhongliang Lv, Wei Li, Qin Zeng

2016

Scoping studies for NBI launch geometries on DEMO

I. Jenkins, C.D. Challis, D.L. Keeling, E. Surrey2016

Investigation of effective thermal conductivity for pebble beds by one-way coupled CFD-DEM method for CFETR WCCB

Lei Chen, Youhua Chen, Kai Huang, Songlin Liu2016

Outgassing measurements for the turn insulation of CFETR poloidal field coils

C. Zou, Y. Song, H. Wu, G. Shen, J. Wei2016

Numerical investigation of the LM MHD flows in a curved duct with an FCI with varying slot locations

Jong Hoon Yang, Yue Yan, Chang Nyung Kim2016

Comparison of W–TiC composite coatings fabricated by atmospheric plasma spraying and supersonic atmospheric plasma spraying

Qing Yu Hou, Lai Ma Luo, Zhen Yi Huang, Ping Wang, Yu Cheng Wu2016

Study of divertor heat flux widths in type-I ELMy H-mode with infra-red thermography on EAST tokamak

Bin Zhang, Xianzu Gong, Kaifu Gan, Liang Wang, Meiwen Chen2016

On the absolute calibration of neutron measurements in fusion reactors

P. Batistoni2016

Potential importance of ultra-deep penetration for operation of IFE power plants

Michaela Martinkova, Mikhail L. Shmatov2016

Tape cast isotropic, fine-grained tungsten for thermo-cyclic loading applications

Mathias Sommerer, Muyuan Li, Ewald Werner, Hubertus von Dewitz, Thomas Arnold2016

Analysis of baffles for stray light reduction in the Thomson scattering diagnostic on EAST

Shumei Xiao, Ailan Hu, Hui Chen, Xiaofeng Han, Junyu Zhao2016

Fission blanket benchmark experiment on spherical assembly of uranium and PE with PE reflector

Tonghua Zhu, Xinxin Lu, Mei Wang, Zijie Han, Rong Liu2016

0-D modeling of SST-1 plasma break-down & start-up using ECRH assisted pre-ionization

Aveg Kumar, Subrata Pradhan2016

Thermo-mechanical and damage analyses of EAST carbon divertor under type-I ELMy H-mode operation

W.X. Li, Y.T. Song, M.Y. Ye, X.B. Peng, C.C. Zhu2016

The benchmark experiment on slab beryllium with D–T neutrons for validation of evaluated nuclear data

Y. Nie, J. Ren, X. Ruan, J. Bao, Z. Zhou2016

Numerical analysis of heat transfer in the first wall of CFETR WCSB blanket

Pinghui Zhao, Weiping Deng, Zhihao Ge, Yuanjie Li2016

Hand-eye coordinative remote maintenance in a tokamak vessel

Qiang Qiu, Kai Gu, Pengfei Wang, Weibang Bai, Qixin Cao2016

Analysis of the effect of the Electron-Beam welding sequence for a fixed manufacturing route using finite element simulations applied to ITER vacuum vessel manufacture

Cristina Martín-Menéndez, Eduardo Rodríguez, Marco Ottolini, Joan Caixas, Julio Guirao2016

Low cycle fatigue design data for India-specific reduced activation ferritic-martensitic (IN-RAFM) steel

K. Mariappan, Vani Shankar, R. Sandhya, K. Laha2016

Hydraulic and thermal testing of different helium cooled irradiation rig models for the IFMIF High Flux Test Module

Christine Klein, Frederik Arbeiter, Thomas Martin, Peter Taubmann2016

Simulations of fusion chamber dynamics and first wall response in a Z-pinch driven fusion–fission hybrid power reactor (Z-FFR)

J.M. Qi, Z. Wang, Y.Y. Chu, Z.H. Li2016

MyView2, a new visualization software tool for analysis of LHD data

Chanho Moon, Mikirou Yoshinuma, Masahiko Emoto, Katsumi Ida2016

Numerical studies on the heat transfer and friction characteristics of the first wall inserted with the screw blade for water cooled ceramic breeder blanket of CFETR

Kecheng Jiang, Xuebin Ma, Xiaoman Cheng, Songlin Liu2016

Conceptual design main progress of EAST Articulated Maintenance Arm (EAMA) system

Shanshuang Shi, Yuntao Song, Yong Cheng, Eric Villedieu, Hongtao Pan2016

A parameter study of time-varying tritium production in solid-type breeder blankets

J. Shimwell, M. Kovari, S. Lilley, S. Zheng, J. McMillan2016

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