中国科学院机构知识库网格
Chinese Academy of Sciences Institutional Repositories Grid
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浏览/检索结果: 共116条,第1-10条 帮助

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Recovery of tungsten and titanium from spent SCR catalyst by sulfuric acid leaching process 期刊论文  OAI收割
WASTE MANAGEMENT, 2023, 卷号: 155, 页码: 338-347
作者:  
Zhao, Chen;  Wang, Chenye;  Wang, Xingrui;  Li, Huiquan;  Chen, Yan
  |  收藏  |  浏览/下载:16/0  |  提交时间:2023/02/24
Evaluation of edge transport and core accumulation of tungsten for CFETR with EMC3-EIRENE and STRAHL 期刊论文  OAI收割
NUCLEAR FUSION, 2022, 卷号: 62
作者:  
Liu, B.;  Dai, S. Y.;  Yang, X. D.;  Chan, V. S.;  Ding, R.
  |  收藏  |  浏览/下载:24/0  |  提交时间:2022/12/22
Modelling of tungsten impurity edge transport and screening for different divertor conditions in EAST 期刊论文  OAI收割
NUCLEAR FUSION, 2022, 卷号: 62
作者:  
  |  收藏  |  浏览/下载:36/0  |  提交时间:2022/12/22
Comparative modeling studies of carbon and tungsten impurity transport in the boundary plasma of EAST with a partially detached divertor condition 期刊论文  OAI收割
NUCLEAR MATERIALS AND ENERGY, 2022, 卷号: 33
作者:  
Xu, Guoliang;  Wang, Hui;  Ding, Rui;  Liu, Xiaoju;  Si, Hang
  |  收藏  |  浏览/下载:36/0  |  提交时间:2022/12/22
Control of tungsten impurity source and edge transport using different gas injection with full tungsten divertor on EAST 期刊论文  OAI收割
NUCLEAR MATERIALS AND ENERGY, 2022, 卷号: 33
作者:  
Ding, R.;  Xu, G. L.;  Wang, H.;  Ding, F.;  Zhang, L.
  |  收藏  |  浏览/下载:26/0  |  提交时间:2022/12/22
Characterizing W sources in the all-W wall, all-RF WEST tokamak environment( * , * ) 期刊论文  OAI收割
PLASMA PHYSICS AND CONTROLLED FUSION, 2022, 卷号: 64
作者:  
Klepper, C. C.;  Unterberg, E. A.;  Marandet, Y.;  Curreli, D.;  Grosjean, A.
  |  收藏  |  浏览/下载:28/0  |  提交时间:2022/12/22
Microstructure and mechanical properties of in-situ formed ZrC nanoparticles dispersion-strengthened tungsten alloy 期刊论文  OAI收割
INTERNATIONAL JOURNAL OF REFRACTORY METALS & HARD MATERIALS, 2022, 卷号: 107
作者:  
Cheng, X.;  Jing, K.;  Xie, Z. M.;  Liu, R.;  Wu, X. B.
  |  收藏  |  浏览/下载:23/0  |  提交时间:2022/12/23
Divertor plasma behaviors with neon seeding at different locations on EAST with ITER-like divertor 期刊论文  OAI收割
NUCLEAR FUSION, 2022, 卷号: 62
作者:  
Meng, L. Y.;  Wang, L.;  Wang, H. Q.;  Deng, G. Z.;  Si, H.
  |  收藏  |  浏览/下载:25/0  |  提交时间:2022/12/22
Achievements of actively controlled divertor detachment compatible with sustained high confinement core in DIII-D and EAST 期刊论文  OAI收割
NUCLEAR FUSION, 2022, 卷号: 62
作者:  
Wang, L.;  Wang, H. Q.;  Eldon, D.;  Yuan, Q. P.;  Ding, S.
  |  收藏  |  浏览/下载:47/0  |  提交时间:2022/05/16
Effect of divertor plasma-facing materials and drift on the power decay width in the scrape-off layer and divertor on EAST 期刊论文  OAI收割
NUCLEAR FUSION, 2022, 卷号: 62
作者:  
Zhang, Chen;  Sang, Chaofeng;  Wang, Liang;  Zhang, Yanjie;  Li, Nami
  |  收藏  |  浏览/下载:21/0  |  提交时间:2022/12/23