机构

• 合肥物质科学研究院 [12]

采集方式

• OAI收割 [12]

内容类型

• 期刊论文 [12]

发表日期

• 2022 [3]
• 2021 [2]
• 2020 [2]
• 2018 [3]
• 2017 [1]
• 2016 [1]
• 更多

学科主题

筛选

浏览/检索结果: 共12条，第1-10条 帮助 条数/页： 5101520253035404550556065707580859095100 排序方式： 请选择题名升序题名降序提交时间升序提交时间降序作者升序作者降序发表日期升序发表日期降序 Updates on CEA Design and Experimental Activities on EU DEMO TF System 期刊论文  OAI收割 IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2022, 卷号: 32 作者:  Zani, L.;  Bonne, F.;  Corato, V.;  Decool, P.;  Hertout, P.   |  收藏  |  浏览/下载：41/0  |  提交时间：2022/12/23 Conductors  Stress  Superconducting magnets  Toroidal magnetic fields  Europe  Costs  Windings  DEMO  LTS  Nb3Sn  nuclear fusion  super- conducting magnets  TF coils   Operating a full tungsten actively cooled tokamak: overview of WEST first phase of operation 期刊论文  OAI收割 NUCLEAR FUSION, 2022, 卷号: 62 作者:  Bucalossi, J.;  Achard, J.;  Agullo, O.;  Alarcon, T.;  Allegretti, L.   |  收藏  |  浏览/下载：90/0  |  提交时间：2022/03/21 nuclear fusion  magnetic confinement  tokamak physics  divertor  WEST  ITER  DEMO   Status of the WEST travelling wave array antenna design and results from the high power mock-up 期刊论文  OAI收割 NUCLEAR FUSION, 2022, 卷号: 62 作者:  Ragona, R.;  Durodie, F.;  Messiaen, A.;  Ongena, J.;  Van Schoor, M.   |  收藏  |  浏览/下载：41/0  |  提交时间：2022/02/14 travelling wave  ICRH  combline  WEST  DEMO   Design and thermal-structural analysis of a high power ICRH travelling wave array antennas 期刊论文  OAI收割 FUSION ENGINEERING AND DESIGN, 2021, 卷号: 166 作者:  Batal, T.;  Ragona, R.;  Hillairet, J.;  Yu, C.;  Bernard, J-M   |  收藏  |  浏览/下载：36/0  |  提交时间：2021/06/15 Travelling wave antenna  Heating system  Ion cyclotron resonance heating  DEMO  Virtual reality  Thermal and structural analysis   New designs of target and cooling scheme for water cooled divertor in DEMO 期刊论文  OAI收割 NUCLEAR FUSION, 2021, 卷号: 61 作者:  Qian, X. Y.;  Peng, X. B.;  Song, Y. T.;  Mao, X.;  Liu, P.   |  收藏  |  浏览/下载：36/0  |  提交时间：2021/03/15 DEMO  divertor  water cooled target  cooling circuit  structural design  thermal-hydraulics   Summary of the 3rd IAEA technical meeting on divertor concepts 期刊论文  OAI收割 NUCLEAR FUSION, 2020, 卷号: 60 作者:  Barbarino, Matteo;  Leonard, Anthony;  Asakura, Nobuyuki N.;  Jakubowski, Marcin;  Kobayashi, Masahiro   |  收藏  |  浏览/下载：50/0  |  提交时间：2020/10/26 divertor and confinement  radiative power exhaust  scrape-off layer and divertor physics  steady state operation and transient heat loads  plasma facing components materials and heat exhaust for steady state operation  divertors for DEMO and reactors   Progress in the conceptual design of the CFETR toroidal field coil with rectangular conductors 期刊论文  OAI收割 NUCLEAR FUSION, 2020, 卷号: 60 作者:     |  收藏  |  浏览/下载：45/0  |  提交时间：2020/11/26 tokamak  DEMO  superconducting magnet  TF  cable-in-conduit conductor  electromagnetic load  mechanical analysis   EMC3-EIRENE modeling of edge plasma to improve the ICRF coupling with local gas puffing in DEMO 期刊论文  OAI收割 NUCLEAR FUSION, 2018, 卷号: 58, 期号: 12, 页码: 11 作者:  Zhang, Wei;  Franke, Thomas;  Noterdaeme, Jean-Marie;  Van Eester, Dirk   |  收藏  |  浏览/下载：31/0  |  提交时间：2019/12/20 scrape-off layer  ICRF coupling  DEMO  local gas puffing   Investigation on the Effect of Tritium Breeding Ratio Using Temperature Control Mechanism for DEMO Blanket 期刊论文  OAI收割 IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 6, 页码: 2277-2280 作者:  Qiu, Yang;  Zhang, Jie;  Liu, Changle;  Yao, Damao;  Gao, Xiang   |  收藏  |  浏览/下载：23/0  |  提交时间：2019/11/12 Breeding blanket  demonstrate power plant (DEMO)  temperature control mechanism (TCM)  tritium breeding ratio (TBR)   Current Status and Progress on the Shielding Blanket of CFETR 期刊论文  OAI收割 IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 5, 页码: 1417-1421 作者:  Liu, Changle;  Yang, Hao;  Zhang, Jie;  Zhang, Jianzhong;  Li, Lei   |  收藏  |  浏览/下载：20/0  |  提交时间：2019/08/23 Chinese fusion engineering test reactor (CFETR)  demonstration reactors (DEMO)  neutronics  shielding blanket (SB)