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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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Adaptive fuzzy PID control of high-speed on-off valve for position control system used in water hydraulic manipulators

Xing Yang, Defa Wu, Chenglong Wang, Chuanqi Gao, Yinshui Liu2024

Thermal-hydraulic assessment of the ITER IBED PHTS

E. Vallone, G. Agnello, L. Basili, A. Ciampichetti, F.L. Venturi2024

A remote detection method for leak location of external ports in a tokamak: Theory and preliminary experimental validation

Hailin Bi, Kunru Fu, Chunpeng Cheng, Guizhong Zuo, Wudi Wang2024

Position estimation of current-carrying filament using different magnetic sensors in ADITYA-U tokamak

Rohit Kumar, Harshita Raj, Suman Aich, Tanmay Macwan, J. Ghosh2024

Design and analysis of redundant electro-hydraulic-driven manipulator for tokamak vacuum vessel

Daoan Kang, Bangmeng Wang, Chao Huang, Dingan Song, Pengyuan Li2024

Measurement of pressure drop of purge gas flow in unitary and binary pebble beds

Yong Liu, Yong Chen, Cong Wang, Lei Chen, Songlin Liu2024

Investigation of radiation power and carbon evaporation in infrared sensor bolometer

Dongjae Kwak, Dong-Kwon Kim, Min Uk Lee, Jaewook Kim, Gunsu S. Yun2024

Signal-distribution-based crack detection for divertor monoblock inspection using eddy current testing

Fanwei Yu, Takuma Tomizawa, Noritaka Yusa, Masayuki Tokitani2024

Design of a multi-energy soft X-ray diagnostic for profile measurements during long-pulse operation in the WEST tokamak

O. Chellaï, L.F. Delgado-Aparicio, J. Wallace, T. Barbui, P. Malard2024

Development of lower manipulator system for breeding blanket maintenance within large port-based tokamaks

Marcell Málics, László Poszovecz, Aditya Sinha, Ian Chiang, Imre Katona2024

Blanket test facility for mockup testing on water cooled ceramic breeder blanket system

Takuya Katagiri, Wenhai Guan, Atsushi Wakasa, Motoki Nakajima, Hiroyasu Tanigawa2024

Deuterium enrichment by proton exchange membrane water electrolysis with electrolyte circulation

Ibuki Sato, Koichiro Furusawa, Mikito Ueda, Hisayoshi Matsushima2024

Reducing the user burden when running MELCOR for accident analysis for a tokamak

G. Karajgikar, J.J. Nebrensky2024

Construction of GVR weight windows maps from very low density transport simulations

Gonzalo Farga-Niñoles, Francisco Ogando, Javier Alguacil, Patrick Sauvan2024

Thermal and structural analysis of the DONES target system under steady state and transient loading conditions

I. Catanzaro, P. Arena, D. Bernardi, G. Bongiovì, E. Vallone2024

Deuterium permeation of low-activation vanadium alloys possible for reuse in a short time in fusion reactors

Aoi Yoshizawa, Yuji Yamauchi, Takuya Nagasaka, Satoshi Tomioka, Naoki Higashi2024

Study on hot isostatic pressing conditions of ARAA for fabrication of the breeding blanket first wall

Hyoseong Gwon, Yunsong Jung, Yi-Hyun Park, Jae-Sung Yoon, Seungyon Cho2024

Assessment of different lifting devices for the shipping bays for DONES main building

Yan Wang, Martin Mittwollen2024

Neural network-based source biasing to speed-up challenging MCNP simulations

E. Martínez-Fernández, J. Alguacil, J. Sanz, R. Juárez2024

Progress and challenges of the ECH transmission line design for DTT

A. Moro, A. Bruschi, F. Fanale, P. Fanelli, E. Vassallo2024

Material flow planning in fusion test facilities

Timo Lehmann, Georg Fischer, Felix Rauscher, Sebastian Köhler, Fernando Arranz2024

A review of pipe cutting, welding, and NDE technologies for use in fusion devices

Yao Ren, Robert Skilton2024

Development of real-time density feedback control on MAST-U in L-mode

G.L. Derks, B. Kool, C. Vincent, S. Elmore, M. van Berkel2024

Development of potassium doped tungsten plate for fusion reactor applications

Shuhei Nogami, Naoya Matsuta, Kei Miura, Kenta Okutani, Tomohiro Takida2024

First-principles study of the energetics of Fe interstitial clusters in vanadium

Xing Wang, Pengbo Zhang, Guofeng Li, Mingliang Wei, Yichao Wang2024

Re-evaluation of shielding ability and induced activity of KSTAR with increased neutron yields

UkJae Lee, Nam-Suk Jung, Hee-Seock Lee, Hee-Soo Kim2024

Overview of European efforts and advances in Stellarator power plant studies

Felix Warmer, J. Alguacil, D. Biek, T. Bogaarts, F.R. Urgorri2024

Free boundary equilibrium determination of HL-3 discharges

Y.Y. Zhong, L. Xue, W.L. Zhong, J.X. Li, H. Heumann2024

Development of a real-time digital pulse acquisition and processing algorithm for compact neutron spectrometer on EAST

Yong-Qiang Zhang, Li-Qun Hu, Wei Lu, Guo-Qiang Zhong, Qiang Li2024

Key technologies of manufacturing and testing for the ITER blanket shield block

Sa-Woong Kim, Si-Kun Chung, Jun-Sung Chang, Duck-Hoi Kim, Ki-Jung Jung2024

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