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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

Strain rate dependence of tensile properties of tungsten alloys for plasma-facing components in fusion reactors

Makoto Fukuda, Tsunenori Tabata, Akira Hasegawa, Shuhei Nogami, Takeo Muroga2016

Numerical analysis of high-speed Lithium jet flow under vacuum conditions

Sergej Gordeev, Friedrich Groeschel, Robert Stieglitz2016

Hydrogen permeation through Flinabe fluoride molten salts for blanket candidates

Ryosuke Nishiumi, Satoshi Fukada, Akira Nakamura, Kazunari Katayama2016

A new integral experiment on copper with DT neutron source at JAEA/FNS

Saerom Kwon, Satoshi Sato, Masayuki Ohta, Kentaro Ochiai, Chikara Konno2016

Safety studies of plasma-wall events with AINA code for Japanese DEMO

J.C. Rivas, M. Nakamura, Y. Someya, K. Hoshino, M. Fabbri2016

New remarks on KERMA factors and DPA cross section data in ACE files

Chikara Konno, Satoshi Sato, Masayuki Ohta, Saerom Kwon, Kentaro Ochiai

2016

Integral experiment on molybdenum with DT neutrons at JAEA/FNS

Masayuki Ohta, Satoshi Sato, Saerom Kwon, Kentaro Ochiai, Chikara Konno2016

Progress of R&D on water cooled ceramic breeder for ITER test blanket system and DEMO

Yoshinori Kawamura, Hisashi Tanigawa, Takanori Hirose, Mikio Enoeda, Toshihiko Yamanishi2016

Evaluation of impacts of stress triaxiality on plastic deformability of RAFM steel using various types of tensile specimen

Taichiro Kato, Mitsuru Ohata, Shuhei Nogami, Hiroyasu Tanigawa2016

Comparison of current density profiles based on particle orbit-driven current in steady-state plasma on QUEST

Md Mahbub Alam, Kazuo Nakamura, Fan Xia, Osamu Mitarai, Takahiro Nagata2016

Configuration management of the EU DEMO conceptual design data

Botond Meszaros, Mark Shannon, Domenico Marzullo, Colin Woodley, Giuseppe Di Gironimo2016

Isotope exchange reaction of tritium on precious metal catalyst based on cation-exchanged mordenite for blanket tritium recovery

Yoshinori Kawamura, Takumi Hayashi, Toshihiko Yamanishi2016

Theoretical studies of MHD flows in support to HCLL design activities

L. Bühler, C. Mistrangelo2016

Characteristics of nickel and iron diffusion in molten lead–17lithium alloy

Yun Gao, Minoru Takahashi, Masao Nomura, Takashi Nozawa2016

Conceptual design studies for the European DEMO divertor: Rationale and first results

J.H. You, G. Mazzone, E. Visca, Ch. Bachmann, V. Widak2016

Development of manufacturing technology for ITER TF Coil Structure

Takeru Sakurai, Masahide Iguchi, Masataka Nakahira, Takashi Inagaki, Norikiyo Koizumi2016

Electromagnetic analyses and optimization for slit configuration of ITER blanket shield block

Weishan Kang, Jiming Chen, Jihong Wu, Erwu Niu2016

Engineering design and analysis of Indian LLCB TBM set

S. Ranjithkumar, Deepak Sharma, Paritosh Chaudhuri, Chandan Danani, K.N. Vyas2016

Methodology for accident analyses of fusion breeder blankets and its application to helium-cooled pebble bed blanket

Dobromir Panayotov, Andrew Grief, Brad J. Merrill, Paul Humrickhouse, Richard Scott2016

Advanced β-ray-induced X-ray spectrometry for non-destructive measurement of tritium retained in fusion related materials

Masao Matsuyama, Shinsuke Abe2016

Reducing beryllium content in mixed bed solid-type breeder blankets

J. Shimwell, S. Lilley, L. Morgan, L. Packer, J. McMillan2016

An integrated model for the assessment of unmitigated fault events in ITER's superconducting magnets

S. McIntosh, A. Holmes, K. Cave-Ayland, A. Ash, N. Mitchell2016

Shutdown dose rate analysis of European test blanket modules shields in ITER Equatorial Port #16

Rafael Juárez, Patrick Sauvan, Lucia Perez, Dobromir Panayotov, Javier Sanz2016

Effect of microstructural anisotropy on the mechanical properties of K-doped tungsten rods for plasma facing components

Shuhei Nogami, Wenhai Guan, Makoto Fukuda, Akira Hasegawa2016

Experimental investigation on heat transfer of HEMJ type divertor with narrow gap between nozzle and impingement surface

Takehiko Yokomine, Ken Oohara, Tomoaki Kunugi2016

Tensile and fatigue properties of potassium doped and rhenium containing tungsten rods for fusion reactor applications

Wenhai Guan, Shuhei Nogami, Makoto Fukuda, Akira Hasegawa2016

Accident analyses of selected postulated events for safety assessment of Indian LLCB TBS in ITER

K.T. Sandeep, Vilas Chaudhari2016

Analysis of plasma equilibrium based on orbit-driven current density profile in steady-state plasma on QUEST

K. Nakamura, M.M. Alam, Y.Z. Jiang, O. Mitarai, A. Fukuyama2016

Overview of LLCB TBM design and R&D activities in India

E. Rajendra Kumar, K.N. Vyas, T. Jayakumar2016

Feasibility study of a neutron activation system for EU test blanket systems

Kuo Tian, Pattrick Calderoni, Bradut-Eugen Ghidersa, Axel Klix2016

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