×
验证码:
换一张
忘记密码?
记住我
CORC
首页
科研机构
检索
知识图谱
申请加入
托管服务
登录
注册
在结果中检索
科研机构
北京航空航天大学 [1]
金属研究所 [1]
宁波材料技术与工程研... [1]
上海大学 [1]
近代物理研究所 [1]
内容类型
期刊论文 [4]
会议论文 [1]
发表日期
2018 [5]
学科主题
Chemistry [1]
Materials ... [1]
Materials ... [1]
Nuclear Sc... [1]
Science & ... [1]
×
知识图谱
CORC
开始提交
已提交作品
待认领作品
已认领作品
未提交全文
收藏管理
QQ客服
官方微博
反馈留言
浏览/检索结果:
共5条,第1-5条
帮助
限定条件
发表日期:2018
已选(
0
)
清除
条数/页:
5
10
15
20
25
30
35
40
45
50
55
60
65
70
75
80
85
90
95
100
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
Microstructural evolution of epitaxial Ti3AlC2 film on sapphire under ion irradiation and nanoindentation-induced deformation
期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2018, 卷号: 509, 页码: 181-187
作者:
Huang, Qing
;
Wang, Ji
;
Shao, Tao
;
Ren, Donglou
;
Liu, Shaoshuai
收藏
  |  
浏览/下载:38/0
  |  
提交时间:2018/10/08
Ion irradiation
Accident tolerant fuels
Fuel cladding coating
Ti3AlC2
MAX phase film
Structural, mechanical and corrosion studies of Cr-rich inclusions in 152 cladding of dissimilar metal weld joint
期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2018, 卷号: 498, 页码: 9-19
作者:
Li, YF
;
Wang, JQ
;
Han, EH
;
Yang, CD
;
Wang, JQ (reprint author), Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Liaoning, Peoples R China.
收藏
  |  
浏览/下载:35/0
  |  
提交时间:2018/06/05
Pressurized-water Reactors
Environmentally-assisted Cracking
Safe-end
Quantitative Assessment
Secondary-side
Residual-stresses
High-temperature
Fusion Boundary
Base Alloys
Part 1
Microstructural evolution of epitaxial Ti3AlC2 film on sapphire under ion irradiation and nanoindentation-induced deformation
期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2018, 卷号: 509, 页码: 181-187
作者:
Wang, Ji
;
Liu, Shaoshuai
;
Ren, Donglou
;
Shao, Tao
;
Eklund, Per
收藏
  |  
浏览/下载:134/0
  |  
提交时间:2018/12/04
Accident Tolerant Fuels
Max Phases
Radiation Tolerance
Neutron-irradiation
m(n+1)Ax(n) Phases
Thin-films
Deposition
Ti3sic2
Ti2alc
Ceramics
Distribution and Characteristics of Oxide Films Formed on Stainless Steel Cladding on Low Alloy Steel in Simulated PWR Primary Water Environments
会议论文
PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOL 2, 2018-01-01
作者:
Xiong, Qi[1]
;
Li, Hongjuan[2]
;
Lu, Zhanpeng[3]
;
Chen, Junjie[4]
;
Xiao, Qian[5]
收藏
  |  
浏览/下载:11/0
  |  
提交时间:2019/04/22
Stainless steel cladding
Pressurized water reactor
Low alloy steel
Oxide film
High temperature water
Analysis of operating characteristics of IPWR under natural circulation
期刊论文
KERNTECHNIK, 2018, 卷号: 83, 页码: 439-450
作者:
Zhu, H.
;
Zhang, S.
;
Xia, G.
;
Peng, M.
收藏
  |  
浏览/下载:7/0
  |  
提交时间:2019/12/30
Coolants
Pressurized water reactors
Safety engineering
Steam
Two phase flow
Core outlet temperature
Forced circulations
Integrated pressurized water reactors
Natural circulation
Operating characteristics
Steam temperature
Thermal hydraulics
Two-phase flow instabilities
Natural convection
©版权所有 ©2017 CSpace - Powered by
CSpace