中国科学院机构知识库网格
Chinese Academy of Sciences Institutional Repositories Grid
首页 机构 成果 学者
  
  1. CAS IR Grid
机构
采集方式
内容类型
发表日期
学科主题
筛选

浏览/检索结果: 共7条，第1-7条 帮助

条数/页： 排序方式：
Long-term plasma exposure of ITER-like W/Cu monoblocks with pre-damaged surfaces in EAST experiments 期刊论文  OAI收割
NUCLEAR FUSION, 2024, 卷号: 64
作者:  Guo, Zongxiao;  Zhu, Dahuan;  Yan, Rong;  Xuan, Chuannan;  Wang, Baoguo
  |  收藏  |  浏览/下载：3/0  |  提交时间：2024/11/20
Studies of material deposition on the graphite divertor tile after the 2019 experimental campaign in EAST 期刊论文  OAI收割
NUCLEAR MATERIALS AND ENERGY, 2022, 卷号: 33
作者:  Zheng, Wei;  Yan, Rong;  Ding, Rui;  Gao, Binfu;  Wang, Baoguo
  |  收藏  |  浏览/下载：37/0  |  提交时间：2022/12/22
Studies of material migration and deposition after the 2017 experimental campaign in EAST 期刊论文  OAI收割
NUCLEAR MATERIALS AND ENERGY, 2022, 卷号: 30
作者:  Yan, Rong;  Peng, Jiao;  Li, Changjun;  Xu, Guoliang;  Ding, Rui
  |  收藏  |  浏览/下载：91/0  |  提交时间：2022/01/25
Impact of W monoblock damage on EAST operations in recent campaigns 期刊论文  OAI收割
FUSION ENGINEERING AND DESIGN, 2021, 卷号: 169
作者:  Binfu, Gao;  Rui, Ding;  Ling, Zhang;  Changjun, Li;  Hai, Xie
  |  收藏  |  浏览/下载：43/0  |  提交时间：2021/08/30
Result and discussion on the evolution of in-situ leading edge-induced melting on W divertor targets in EAST 期刊论文  OAI收割
NUCLEAR MATERIALS AND ENERGY, 2021, 卷号: 27
作者:  Lei, Yang;  Zhu, Dahuan;  Li, Changjun;  GeSangZhouMa;  Gao, Binfu
  |  收藏  |  浏览/下载：41/0  |  提交时间：2021/08/31
Plasma-facing components damage and its effects on plasma performance in EAST tokamak 期刊论文  OAI收割
FUSION ENGINEERING AND DESIGN, 2020, 卷号: 156
作者:  Gao, Binfu;  Ding, Rui;  Xie, Hai;  Zeng, Long;  Zhang, Ling
  |  收藏  |  浏览/下载：32/0  |  提交时间：2020/11/26
Characterization of the in situ leading-edge-induced melting on the ITER-like tungsten divertor in EAST 期刊论文  OAI收割
NUCLEAR FUSION, 2020, 卷号: 60
作者:  Zhu, Dahuan;  Li, Changjun;  Ding, Rui;  Wang, Baoguo;  Chen, Junling
  |  收藏  |  浏览/下载：33/0  |  提交时间：2020/11/26