図版検索 AI要約 wiki 日本の研究装置ジャーナル ChatGPT About

© 2026 FUSIONPAPERS

About 法務情報

ジャーナル一覧に戻る

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

AI解説分析論文一覧

キーワード検索

年

AI要約

全 15,142 件の論文

並び順:新しい順古い順被引用数順

Numerical simulation of liquid metal MHD flows in a conducting rectangular duct with triangular strips

Lang Yang, Jie Mao, Baolong Xiong2021

Effect of temperature on the growth and surface bursting of He nano-bubbles in W under fusion-relevant He ion irradiations

Chunjie Niu, Yang Zhang, Yunqiu Cui, Xiaoping Li, Dongping Liu2021

Effect of the LEHs film transmissivity on spherical hohlraum cryogenic target after the shield is removed

Peng Tang, Qilong Liao, Yunya Dai, Xiaoyuru Chen2021

Neutronic analyses of port impact on blankets and superconducting coils of CFETR

Wei Shi, Wei Li, Qin Zeng, Hongli Chen2021

Identification of precipitate phases in CLAM steel

Yinzhong Shen, Xiaoling Zhou, Xi Huang, Zhijun Fan, Xingjian Shi2021

Tomographic reconstruction of emissive profile in the divertor region for the visible light imaging diagnostic on Experimental Advanced Superconducting Tokamak

Zhiyuan Lu, Shifeng Mao, Jianhua Yang, Tingfeng Ming, Minyou Ye2021

Effects of bed dimension, friction coefficient and pebble size distribution on the packing structures of the pebble bed for solid tritium breeder blanket

Yongjin Feng, Baoping Gong, Hao Cheng, Xiaofang Luo, Xiaoyu Wang2021

Numerical simulations with RELAP5-3D of the first experimental campaign on In-box LOCA transient for HCLL TBS

A. Venturini, M. Utili, N. Forgione2021

Numerical simulations of radioactive dust particle releases during a Loss Of Vacuum Accident in a nuclear fusion reactor

Riccardo Rossi, Pasqualino Gaudio, Luca Martellucci, Andrea Malizia2021

Characterization of the soft zone in dissimilar welds joint of 2.25Cr-1Mo and lean duplex LDX2101 steel

C. Pandey, J.G. Thakare, P.K. Taraphdar, P. Kumar, S. Sirohi2021

An adaptive optimization reverse regulation method for neutron spectrum based on standardized response module

Chenglong Cao, Quan Gan2021

Design and characteristics of a modular integrated power supply for the system of flashlamp-pumped in inertial confinement fusion

Bin Yu, Yuan Pan, Lee Li, Jiaming Xiong, Haibo Wu2021

Performance of the first neutral beam injector at the Wendelstein 7-X stellarator

Annabelle Spanier, Dirk Hartmann, Simppa Äkäslompolo, Oliver Ford, Robert C. Wolf2021

RF discharge mirror cleaning for ITER optical diagnostics using 60 MHz very high frequency

L. Marot, L. Moser, R. Steiner, W. Erni, E. Meyer2021

Key manufacturing technologies of the CFETR 1/8 vacuum vessel sector mockup

Jianguo Ma, Jiefeng Wu, Zhihong Liu, Rui Wang, Haibiao Ji2021

Accelerated version of NUBEAM capabilities in DIII-D using neural networks

Shira M. Morosohk, Mark D. Boyer, Eugenio Schuster2021

Effect of ITER CS and PF magnets on EM loads outside vacuum vessel at plasma disruption events

D.N. Arslanova, A.V. Belov, E.I. Gapionok, V.P. Kukhtin, S.E. Sytchevsky2021

Assessment of SIMMER-III code in predicting Water Cooled Lithium Lead Breeding Blanket “in-box-Loss of Coolant Accident”

Marica Eboli, Nicola Forgione, Alessandro Del Nevo2021

A neutronics probe ball method on tritium generation rate simulation for a nuclear fusion reactor blanket

Yang Qiu, Changle Liu2021

Flush-mounted Langmuir probes in the WEST tokamak divertor

R. Dejarnac, D. Sestak, J.P. Gunn, M. Firdaouss, H. Roche2021

Manufacturing design of typical attachments in the vacuum vessel of ITER

Yugyeong Kim, Mikhail Privalov, Juntao Jing, Arnaud Mestric2021

Oxygen interaction with alloying elements (Cr/Ni) and vacancies in dilute austenitic iron alloys: A first-principles study

Pengbo Zhang, Tingting Zou, Dan Sun, Yan Yin, Jijun Zhao2021

In-situ oxidation of aluminized stainless-steel to form alumina as tritium permeation barrier coating

Ran Yin, Lulu Hu, Jun Tang, Tao Cheng, Feng Ren2021

Preliminary thermal-hydraulic analysis of the EU-DEMO Helium-Cooled Pebble Bed fusion reactor by using the RELAP5-3D system code

Salvatore D’Amico, Pietro Alessandro Di Maio, Xue Zhou Jin, Francisco Alberto Hernández Gonzalez, Guangming Zhou2021

Electrochemical measurements of the corrosion of pure Fe and JLF-1 steel in HF-containing molten FLiNaK salt

Gaku Yamazaki, Takuya Nagasaka, Juro Yagi, Takuya Goto, Akio Sagara2021

Fabrication of ITER Divertor Cassette Body prototypes

Laurent Guerrini, Bruno Riccardi, José Andrade, Frederic Escourbiac, Patrick Lorenzetto2021

ARC reactor: Radioactivity safety assessment and preliminary environmental impact study

Massimo Zucchetti, Zachary Hartwig, Samuele Meschini, Stefano Segantin, Dennis Whyte2021

Hydrogen permeation behavior through tungsten deposition layer

Hideki Ito, Kazunari Katayama, Daisuke Mori, Yuki Hara, Makoto Oya2021

Voltage hold off test of the insulating supports for the plasma grid mask of SPIDER

Alberto Maistrello, Mauro Recchia, Nicolò Marconato, Tommaso Patton, Gianluigi Serianni2021

Maximum allowable fluid velocity and concern on piping stability of ITER Tokamak cooling water system

前へ 1...98 99 100 101 102 103 104...505 次へ