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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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ENEA ultrasonic test on plasma facing units

Selanna Roccella, Andrea Reale, Angelo Tatì, Eliseo Visca, Pierre Gavila2019

Operation of probe heads on the Multi-Purpose-Manipulator at W7-X in OP 1.2a

P. Drews, C. Killer, A. Knieps, M. Henkel, T. Schröder2019

In-vessel viewing system prototype performance measurements and simulation of measurement quality across the ITER in-vessel components

Thomas Siegel, Efstathios Kolokotronis, Andrés Cifuentes, Paloma Matia-Hernando, Roger Reichle2019

New data acquisition control software developments for the simultaneous control of ten intelligent overview video cameras at W7-X

Tamás Szabolics, Gábor Cseh, Gábor Kocsis, Tamás Szepesi, Torsten Bluhm2019

Comparison of approaches to the electromagnetic analysis of COMPASS-U vacuum vessel during fast transients

V.V. Yanovskiy, N. Isernia, V.D. Pustovitov, F. Villone, I. Zammuto2019

Industry supported improved design of DEMO BoP for HCPB BB concept with energy storage system

Evaldas Bubelis, Wolfgang Hering, Sara Perez-Martin2019

Microstructural comparison of Oxide Dispersion Strengthened Fe-14Cr steels produced by HIP and SPS

David Pazos, Marta Suárez, Adolfo Fernández, Pilar Fernández, Nerea Ordás2019

Assessment of the activation induced by neutron irradiation in K-DEMO and thermal response under the decay heat

Beom Seok Kim, Byung Chul Kim, Kihak Im, Hong-Tack Kim, Jongsung Park2019

Tritium transport model at breeder unit level for HCLL breeding blanket

Raffaella Testoni, Luigi Candido, Marco Utili, Massimo Zucchetti2019

Heat management for water-hydraulic systems at ITER remote handling

J. Väyrynen, L. Aha, J. Mattila, S. Esqué, R. Sharratt2019

Neural network based prediction of heat flux profiles on STRIKE

Rita S. Delogu, Augusto Montisci, Antonio Pimazzoni, Gianluigi Serianni, Giuliana Sias2019

Strategy and methods on thermal integrity management of the ITER Thermal Shield

Germán Pérez-Pichel, Térénig Arzoumanian, Chang Hyun Noh, Manoj Panchal, Chang Ho Choi2019

Conceptual studies on spectroscopy and radiation diagnostic systems for plasma control on DEMO

W. Gonzalez, W. Biel, Ph. Mertens, M. Tokar, Ch. Linsmeier2019

The development of technology of Be/CuCrZr joining using induction brazing

A. Gervash, R. Giniyatulin, T. Guryeva, D. Glazunov, O. Sevryukov2019

Numerical investigation of mechanical and thermal characteristics of binary-sized pebble beds using discrete element method

Youngmin Lee, Suhwan Yu, Mu-Young Ahn, Yi-Hyun Park, Dongwoo Sohn2019

Engineering and integration risks arising from advanced magnetic divertor configurations

R. Kembleton, G. Federici, R. Ambrosino, F. Maviglia, M. Suiko2019

Upgraded concepts and design of an in vessel inspection system for fusion reactors

Carlo Neri, Mario Ferri De Collibus, Paolo Rossi, Giampiero Mugnaini, Marcello Nuvoli2019

Development of tungsten armored high heat flux plasma facing components for ITER like divertor application

K. Premjit Singh, S.S. Khirwadkar, Nikunj Patel, Prakash Mokaria, Kalpesh Galodiya2019

Methodology for reverse engineering analysis of ITER as-built integrated systems

F. Javier Fuentes, Jean-Jacques Cordier, Pierric Leonard, Lucas Scherrer, Tudorel Popa2019

Software quality management approach for WEST CODAC

J. Colnel, S. Bremond, G. Caulier, P. Moreau, B. Santraine2019

First considerations on the Balance of Plant for a HELIAS fusion power plant

Felix Warmer, Evaldas Bubelis2019

The relationship between structural changes of ceramic coatings and γ-ray irradiation effect on deuterium permeation

Hikari Fujita, Takumi Chikada, Jan Engels, Jumpei Mochizuki, Takayuki Terai2019

Optimal pump regeneration model for fuel cycle of ITER

Suh-Young Lee, Min Ho Chang, Jae-Uk Lee, Sei-Hun Yun, Euy Soo Lee2019

On the effect of stiffening plates configuration on the DEMO Water Cooled Lithium Lead Breeding Blanket module thermo-mechanical behaviour

P.A. Di Maio, P. Arena, G. Bongiovì, I. Catanzaro, R. Forte2019

Recent achievements of the Pd-Ag membrane technologies in tritium extraction system applications

Alessia Santucci, Rodrigo Antunes, Giacomo Bruni, Federica Mallozzi, Mirko Sansovini2019

Acceleration grid power supply conversion system of the MITICA neutral beam injector: On site integration activities and tests

L. Zanotto, M. Dan, V. Toigo, F. Ferrari, C. Panizza2019

The strategy toward realization of the helical fusion reactor FFHR-c1

Junichi Miyazawa, Takuya Goto, Hitoshi Tamura, Teruya Tanaka, Akio Sagara2019

Mechanical properties and microstructure characterization of Eurofer97 steel variants in EUROfusion program

Xiang Chen, Arunodaya Bhattacharya, Mikhail A. Sokolov, Logan N. Clowers, Michael Rieth2019

Thermal-hydraulic analysis for first wall and thermal shield of Divertor Tokamak test facility

Fabio Maviglia, Riccardo De Luca, Selanna Roccella, Giorgio Maddaluno, Eliseo Visca2019

First thermal-hydraulic analysis of a CO2 cooled pebble bed blanket for the EU DEMO

Shuai Wang, Francisco A. Hernández, Guangming Zhou, Hongli Chen2019

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