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浏览/检索结果: 共85条，第1-10条 帮助 限定条件 发表日期：2021    内容类型：期刊论文    专题：合肥物质科学研究院    第一署名单位    第一作者单位    通讯作者单位     已选(0)清除 条数/页：5101520253035404550556065707580859095100   排序方式：请选择作者升序作者降序题名升序题名降序发表日期升序发表日期降序提交时间升序提交时间降序 Occupational Radiation Exposure Estimated for Fusion Demonstration Reactors and Beyond 期刊论文 FUSION SCIENCE AND TECHNOLOGY, 2021 作者:  Guo, Dingqing;  Chen, Chao;  Wang, Zhen;  Lin, Jian;  Zhang, Bing 收藏  |  浏览/下载：44/0  |  提交时间：2022/01/10 Occupational radiation exposure  risk assessment  collective dose  fusion demonstration reactors   RAMI Analysis for PF Power Supply System of ITER 期刊论文 FUSION SCIENCE AND TECHNOLOGY, 2021 作者:  Jiang, Li;  Gao, Ge;  Huang, Zhengyi;  Zhang, Jie;  Wu, Peng 收藏  |  浏览/下载：38/0  |  提交时间：2022/01/10 RAMI  ITER  availability and reliability  poloidal field coil power supply system  IDEFo model   A study on nuclear analysis of the divertor region of the CFETR 期刊论文 PLASMA SCIENCE & TECHNOLOGY, 2021, 卷号: 23 作者:  Saidahmed, Rayyan;  Yao, Damao;  Wu, Qiuran;  Liu, Songlin;  Xu, Tiejun 收藏  |  浏览/下载：25/0  |  提交时间：2021/11/15 CFETR  fusion reactor  divertor  nuclear analysis  divertor region   Effect of tungsten armor on electromagnetic characteristics of blanket for the fusion device under plasma disruption 期刊论文 FUSION ENGINEERING AND DESIGN, 2021, 卷号: 173 作者:  Zhang, Shanwen;  Kong, Min;  Zhu, Lin;  Du, Shuangsong;  Feng, Changle 收藏  |  浏览/下载：47/0  |  提交时间：2021/11/01 Fusion device  First wall  Plasma disruption  Tungsten armor  Eddy current   Preliminary design of real-time plasma control system for CFETR 期刊论文 FUSION ENGINEERING AND DESIGN, 2021, 卷号: 173 作者:  Yuan, Q. P.;  Guo, H. R.;  Yan, L. L.;  Huang, Z. M.;  Huang, J. J. 收藏  |  浏览/下载：54/0  |  提交时间：2021/11/01 Real-time plasma control system  Control framework  PCS software development platform  PCS verification platform   Ex-situ diagnosis of deuterium retention and carbon deposition on shaped tungsten castellated blocks exposed in KSTAR by laser-induced breakdown spectroscopy 期刊论文 FUSION ENGINEERING AND DESIGN, 2021, 卷号: 173 作者:  Sun, Liying;  Wu, Ding;  Li, Cong;  Zhao, Dongye;  Wu, Jing 收藏  |  浏览/下载：64/0  |  提交时间：2021/11/01 Laser-induced breakdown spectroscopy  Plasma-wall interaction  Fuel retention  Carbon deposition  Tungsten divertor  KSTAR   Development of shutdown dose rate calculation code based on cosRMC and application to benchmark analysis 期刊论文 FUSION ENGINEERING AND DESIGN, 2021, 卷号: 173 作者:  Zhang, Xian;  Liu, Shichang;  Lu, Peng;  Zhang, Xiaokang;  Zheng, Yu 收藏  |  浏览/下载：36/0  |  提交时间：2021/11/29 Shutdown dose rate  R2S method  Monte Carlo  cosRMC  ALARA   High heat flux testing of newly developed tungsten components for WEST 期刊论文 FUSION ENGINEERING AND DESIGN, 2021, 卷号: 173 作者:  Pintsuk, G.;  Missirlian, M.;  Luo, G-N;  Li, Q.;  Wang, W. 收藏  |  浏览/下载：46/0  |  提交时间：2021/11/29 WEST  Tungsten divertor  High heat flux   The upgrade of data processing and storage system for EAST NBI 期刊论文 FUSION ENGINEERING AND DESIGN, 2021, 卷号: 173 作者:  Gu, Yu;  Fan, Mengqi;  Zhao, Yuanzhe;  Zhang, Xiaodan 收藏  |  浏览/下载：62/0  |  提交时间：2021/11/29 EPICS  MDSplus  Data processing  Transmission  Storage management   Physics design of new lower tungsten divertor for long-pulse high-power operations in EAST 期刊论文 NUCLEAR FUSION, 2021, 卷号: 61 作者:  Xu, G. S.;  Wang, L.;  Yao, D. M.;  Jia, G. Z.;  Sang, C. F. 收藏  |  浏览/下载：55/0  |  提交时间：2022/01/10 tungsten divertor upgrade  closed divertor concept  plasma-material interaction  divertor detachment  EAST tokamak