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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

公式サイト

Impact Factor

1.7

Citescore

3.7

最新論文

  • Corrigendum to “Improving the Newton cooling model to drive the optimization method for heterogeneous storage of ECRH hot data” [Fusion Engineering and Design 215 (2026) 115715]
  • Corrigendum to “Relativistic effects on stopping power of plasmas with heavy ions” [Fusion Engineering and Design 205 (2024), 114524]
  • Corrigendum to “Initial accident scenario analysis in support of a preliminary DEMO tritium plant design” [Fusion Engineering and Design 189 (2023) 113482]
  • Thermal behaviour of ZrCo getter beds during hydrogen absorption at variable flow rates and concentrations
  • Performance of the W7-X ECRH gyrotron diamond output window at 2 MW operation
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全 15,142 件の論文
並び順:新しい順古い順被引用数順

Investigation of some critical scenarios due to various failures of ICSI Cryogenic Distillation System

George Ana, Nicolae Sofilca, Alina Niculescu, Mirela Draghia2017

Post-test analyses of LIFUS5 Test#3 experiment

Marica Eboli, Alessandro Del Nevo, Nicola Forgione, Maria Teresa Porfiri2017

Dynamic model of ITER Front-End Cryopumps Distribution System: Torus cryopumping and regeneration scenarios

Silvio Giors, Bastien Boussier, Matthias Dremel, Jacek Kosek, Ana Maria Veleiro Blanco2017

An innovative approach for DEMO core fuelling by inboard injection of high-speed pellets

A. Frattolillo, F. Bombarda, Chr. Day, P.T. Lang, B. Pégourié2017

Operational aspects of the JET tritium introduction modules

Ivo S. Carvalho, David Wilson, Tom Keenan, Robert Felton, Sarah Medley2017

Al2O3 coating as barrier against corrosion in Pb-17Li

M. Carmona Gazquez, S. Bassini, T. Hernandez, M. Utili
2017

Lead-lithium facility with superconducting magnet for MHD/HT tests of liquid metal breeder blanket

A.Yu. Hon, I.R. Kirillov, K.A. Komov, O.A. Kovalchuk, E.R. Zapretilina2017

Thermal optimization of the Helium-Cooled Lithium Lead breeding zone layout design regarding TBR enhancement

P. Arena, J. Aubert, G. Aiello, R. Boullon, G. Rampal2017

Thermal-hydraulic design of a DCLL breeding blanket for the EU DEMO

Iván Fernández-Berceruelo, David Rapisarda, Iole Palermo, Luis Maqueda, Ángel Ibarra2017

Performance of tritium analysis system using inorganic-based hydrophobic platinum catalyst

Yuki Edao, Yasunori Iwai, Katsumi Sato, Takumi Hayashi2017

Quantifying TBR uncertainty due to lead nuclear data in HCLL blanket modelling by the Total Monte-Carlo method

F. Thomas, M. Fleming2017

Mercury ring pump proof-of-principle testing in the THESEUS facility

T. Giegerich, C. Day, M. Jäger2017

Thermal analyses of beryllide pebbles in water vapor atmosphere as advanced neutron multipliers

Jae-Hwan Kim, Masaru Nakamichi2017

Changes in mechanical property and microstructure of lithium metatitanate tritium breeder caused by thermal annealing

Yu Otani, Kiyoto Shin-mura, Seiya Ogawa, Tsuyoshi Hoshino, Kazuya Sasaki2017

State of the art and perspective of high-speed pellet injection technology

F. Bombarda, A. Frattolillo, S. Migliori, F. Iannone, S.K. Combs2017

Theoretical and experimental study on effective thermal conductivity of pebble bed for fusion blanket

Hongli Chen, Shuang Wang, Cheng Jin, Shuai Wang, QingQing Xu2017

Li mass loss from Li2TiO3 with excess Li pebbles fabricated by optimized sintering condition

Ryotaro Yamamoto, Kazunari Katayama, Tsuyoshi Hoshino, Toshiharu Takeishi, Satoshi Fukada2017

Review of hydrogen isotopes transport parameters and considerations to corresponding experiments

Axel von der Weth, Frederik Arbeiter, Dmitry Klimenko, Volker Pasler, Georg Schlindwein2017

Pellet injectors for EAST and KSTAR tokamaks

Igor Vinyar, Jiansheng Hu, Soo-Hwan Park, Alexander Lukin, Hong-Tack Kim2017

Mechanical properties of ARAA steel after electron beam welding

Jae Sung Yoon, Suk-Kwon Kim, Eo Hwak Lee, Hyung Gon Jin, Seungyon Cho2017

The European ITER Test Blanket Modules: EUROFER97 material and TBM’s fabrication technologies development and qualification

M. Zmitko, Y. Carin, N. Thomas, M. Simon-Perret, Y. Poitevin2017

Li vaporization properties of candidate materials for tritium breeder with high Li density

Kiyoto Shin-mura, Yu Otani, Seiya Ogawa, Tsuyoshi Hoshino, Kazuya Sasaki2017

Parameter study on helium cooled ceramic breeder blanket neutronics with CFETR integration design platform

Kun Xu, Minyou Ye, Yuntao Song, Bingbing Xu, Shifeng Mao2017

Dynamic simulation of a multicomponent distillation column for D-T separation

Alina Niculescu, Toma Constantin, George Ana, Mirela Draghia2017

Hydrogen inventory control for vanadium by Ti metal powder mixing in molten salt FLiNaK

Juro Yagi, Akio Sagara, Takuya Nagasaka, Teruya Tanaka, Takeo Muroga2017

The coolant purification system in DEMO: Interfaces and requirements

Alessia Santucci, Antonio Frattolillo, Marco Incelli, Silvano Tosti2017

Effect of halogenated gas on detritiation efficiency of detritiation system

Yasunori Iwai, Yuki Edao, Akiko Kondo, Katsumi Sato2017

Development of advanced hydrogen permeation sensors to measure Q2 concentration in lead-lithium eutectic alloy

L. Candido, M. Utili, M. Zucchetti, A. Ciampichetti, P. Calderoni2017

Li2TiO3 powder synthesis by solid-state reaction and pebble fabrication for tritium breeding material

Yi-Hyun Park, Kyung-Mi Min, Seungyon Cho, Mu-Young Ahn, Young-Min Lee2017

On the thermo-mechanical behaviour of DEMO water-cooled lithium lead equatorial outboard blanket module

P.A. Di Maio, P. Arena, G. Bongiovì, P. Chiovaro, M.L. Richiusa2017
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