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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

Materials R&D for a timely DEMO: Key findings and recommendations of the EU Roadmap Materials Assessment Group

Derek Stork, Pietro Agostini, Jean-Louis Boutard, Derek Buckthorpe, Steven J. Zinkle2014

Fusion materials science and technology research opportunities now and during the ITER era

S.J. Zinkle, J.P. Blanchard, R.W. Callis, C.E. Kessel, B.D. Wirth2014

Radiological assessment of the limits and potential of reduced activation ferritic/martensitic steels

Hiroyasu Tanigawa, Yoji Someya, Hideo Sakasegawa, Takanori Hirose, Kentaro Ochiai2014

Neutron irradiation effects on tungsten materials

Akira Hasegawa, Makoto Fukuda, Shuhei Nogami, Kiyohiro Yabuuchi2014

Current status of technology development for fabrication of Indian Test Blanket Module (TBM) of ITER

T. Jayakumar, E. Rajendra Kumar2014

Alternative analysis for fuel storage and delivery in the ITER Tritium Plant

Min Ho Chang, Sei-Hun Yun, Hyun-Goo Kang, Seungyon Cho, Manfred Glugla2014

Fuskite® preliminary experimental tests based on permeation against vacuum for hydrogen recovery as a potential application in Pb15.7Li loop systems

R. Sacristán, G. Veredas, I. Bonjoch, I. Peñalva, F. Legarda2014

Theoretical prediction of thermodynamic properties of tritiated beryllium molecules and application to ITER source term

F. Virot, M. Barrachin, S. Souvi, L. Cantrel2014

Hydrogen and water vapor adsorption properties on cation-exchanged mordenite for use to a tritium recovery system

Yoshinori Kawamura, Yuki Edao, Yasunori Iwai, Takumi Hayashi, Toshihiko Yamanishi2014

Investigation on degradation mechanism of ion exchange membrane immersed in highly concentrated tritiated water under the Broader Approach Activities

Yasunori Iwai, Katsumi Sato, Toshihiko Yamanishi2014

On ion implantation and damage effect in Li2TiO3 as a fusion breeder blanket: A technological approach for degradation testing

E. Carella, M. Leon, T. Sauvage, M. Gonzalez2014

Design and R&D activities of TriPla-CA Consortium in support of ITER Tritium Plant development

I. Cristescu, G. Ana, D. Demange, R. Michling, S. Welte2014

Hydrogen isotope behavior on a water–metal boundary with simultaneous transfer from and to the metal surface

Takumi Hayashi, Kanetsugu Isobe, Hirofumi Nakamura, Kazuhiro Kobayashi, Yoshihiko Yamanishi2014

Tritium retention properties of tungsten, graphite and co-deposited carbon film

Y. Nobuta, Y. Hatano, M. Matsuyama, S. Abe, M. Akiba2014

Parametric analysis of LIBRETTO-4 and 5 in-pile tritium transport model on EcosimPro

Pablo Martínez Alcalde, Carlos Moreno, Ángel Ibarra2014

Towards a physics-integrated view on divertor pumping

Chr. Day, C. Gleason-González, V. Hauer, Y. Igitkhanov, S. Varoutis2014

Hydrogen extraction characteristics of high-temperature proton conductor ceramics for hydrogen isotopes purification and recovery

Tirui Xia, Changshui He, Hongguang Yang, Weiwei Zhao, Liling Yang2014

Risk-based multi-criteria design concept of the ITER SDS getter bed

S.-H. Yun, H.-G. Kang, M.H. Chang, S. Cho, M. Glugla2014

Direct measurement of tritium production rate in LiPb with removed parasitic activities: Preliminary experiments

Tadeusz Kuc, Władysław Pohorecki, Beata Ostachowicz2014

Interaction of tritium and helium with lead–lithium eutectic under reactor irradiation

Irina Tazhibayeva, Timur Kulsartov, Nikolay Barsukov, Yuri Gordienko, Ergazy Kenzhin2014

Use of system code to estimate equilibrium tritium inventory in fusion DT machines, such as ARIES-AT and components testing facilities

C.P.C. Wong, B. Merrill2014

The KALPUREX-process – A new vacuum pumping process for exhaust gases in fusion power plants

Thomas Giegerich, Christian Day2014

Technologies and modelling issues for tritium processing in the European Test Blanket Systems and perspectives for DEMO

I. Ricapito, P. Calderoni, Y. Poitevin, A. Aiello2014

DT neutron irradiation experiment for evaluation of tritium recovery from WCCB blanket

Kentaro Ochiai, Yoshinori Kawamura, Tsuyoshi Hoshino, Yuki Edao, Chikara Konno2014

Measurements of the purge helium pressure drop across pebble beds packed with lithium orthosilicate and glass pebbles

Ali Abou-Sena, Frederik Arbeiter, Lorenzo V. Boccaccini, Georg Schlindwein2014

Characteristics of microstructure and tritium release properties of different kinds of beryllium pebbles for application in tritium breeding modules

P. Kurinskiy, P. Vladimirov, A. Moeslang, R. Rolli, M. Zmitko2014

Influence of magnetic field deformation by ferromagnetic wall materials on MHD flows in pipes and ducts of fusion blankets

Sebastian Ehrhard, Leo Buehler2014

Development of the Helium Cooled Lithium Lead blanket for DEMO

G. Aiello, J. Aubert, N. Jonquères, A. Li Puma, G. Rampal2014

Effect of plasma-sintering consolidation on the reactivity of beryllium

Jae-Hwan Kim, Masaru Nakamichi2014

Corrosion susceptibility comparison of EUROFER steel in contact two lithium silicate breeders

T. Hernández, P. Fernández2014

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