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西安交通大学 [22]
上海应用物理研究所 [6]
山东大学 [6]
大连理工大学 [2]
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期刊论文 [45]
会议论文 [3]
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2018 [48]
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Current Status and Progress on the Shielding Blanket of CFETR
期刊论文
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:9/0
  |  
提交时间:2019/08/23
Chinese fusion engineering test reactor (CFETR)
demonstration reactors (DEMO)
neutronics
shielding blanket (SB)
Effect of Fe2Zr phase on the mechanical properties and fracture behavior of Fe-Cr-W-Zr ferritic alloy
期刊论文
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2018, 卷号: 722, 页码: 173-181
作者:
Jin, XJ
;
Chen, SH
;
Rong, LJ
;
Rong, LJ (reprint author), Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, 72 Wenhua Rd, Shenyang 110016, Liaoning, Peoples R China.
收藏
  |  
浏览/下载:23/0
  |  
提交时间:2018/06/05
Martensitic Steels
Fusion-reactors
Ods Steel
Strength
Deformation
Microstructure
Stability
Zirconium
System
Temperatures
Characteristics of oil shale pyrolysis in a two-stage fluidized bed
期刊论文
CHINESE JOURNAL OF CHEMICAL ENGINEERING, 2018, 卷号: 26, 期号: 2, 页码: 407-414
作者:
Tian, Yong
;
Li, Mengya
;
Lai, Dengguo
;
Chen, Zhaohui
;
Gao, Shiqiu
收藏
  |  
浏览/下载:23/0
  |  
提交时间:2018/06/11
Oil Shale
Pyrolysis
Fluidized-bed
Upgrading
Secondary Cracking
Reactors
Experimental study of wall-to-bed heat transfer in a supercritical water fluidized bed
期刊论文
International Journal of Multiphase Flow, 2018, 卷号: 109, 页码: 26-34
作者:
Zhang, Tianning
;
Lu, Youjun
;
Yao, Liang
收藏
  |  
浏览/下载:3/0
  |  
提交时间:2019/11/19
Dimensionless analysis
Experimental conditions
Fluidized bed reactors
Heat transfer characteristics
Heat transfer correlation
Supercritical water
Temperature and pressures
Temperature range
Investigation on Nonuniformity of Heat Transfer in Triangular Subchannels of Supercritical Water Cooled Reactor
期刊论文
Hedongli Gongcheng/Nuclear Power Engineering, 2018, 卷号: 39, 页码: 33-39
作者:
Wang, Weishu
;
Hou, Yanliang
;
Xu, Weihui
;
Zhu, Xiaojing
;
Bi, Qincheng
收藏
  |  
浏览/下载:7/0
  |  
提交时间:2019/11/19
Circumferential angles
Heat transfer characteristics
Local heat transfer coefficient
Nonuniformity
Pitch-to-diameter ratios
SCWR
Subchannels
Supercritical water cooled reactors
Experimental investigation of entrainment effect on the countercurrent flow in the Hot Leg and Pressurizer Surge Line assembly of third-generation passive nuclear reactors
期刊论文
NUCLEAR ENGINEERING AND DESIGN, 2018, 卷号: 335, 页码: 326-338
作者:
Yu, Jiangtao
;
Zhang, Dalin
;
Shi, Leitai
;
Tian, Wenxi
;
Su, G. H.
收藏
  |  
浏览/下载:2/0
  |  
提交时间:2019/11/19
Hot Leg and Pressurizer Surge Line Assembly
Visual air-water experiments
Third-generation passive nuclear reactors
Entrainment effect
Countercurrent Flow Limitation
Accident process and core thermal response during a station blackout initiated study for small modular reactor
期刊论文
Frontiers in Energy Research, 2018, 卷号: 6
作者:
Yin, Shasha
;
Tian, Yajing
;
Qiu, Suizheng
;
Tian, Ye
;
Fang, Huawei
收藏
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浏览/下载:8/0
  |  
提交时间:2019/11/19
Beyond design basis accident
Core degradation
MELCOR
Melting materials
Safety assessments
Severe accident
Small modular reactors
Thermal-hydraulic response
Experimental investigation of flow and convective heat transfer on a high-Prandtl-number fluid through the nuclear reactor pebble bed core
期刊论文
Applied Thermal Engineering, 2018, 卷号: 145, 页码: 48-57
作者:
Liu, Limin
;
Zhang, Dalin
;
Li, Linfeng
;
Yang, Yicheng
;
Wang, Chenglong
收藏
  |  
浏览/下载:4/0
  |  
提交时间:2019/11/19
Experimental investigation
Fluoride-salt-cooled high-temperature reactors
High-Prandtl-number fluid
Pebble bed
Design of Space Reactor Radiation Radiator
期刊论文
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2018, 卷号: 52, 页码: 788-794
作者:
Liu, Xiao
;
Zhang, Wenwen
;
Wang, Chenglong
;
Zhang, Dalin
;
Tian, Wenxi
收藏
  |  
浏览/下载:5/0
  |  
提交时间:2019/11/19
Condensation section
Convective heat transfer
Coolant flow rates
Coolant temperature
Flow direction
Heat transfer model
Preliminary design
Space reactors
Neutronics and thermal hydraulics analysis of a conceptual ultra-high temperature MHD cermet fuel core for nuclear electric propulsion
期刊论文
Frontiers in Energy Research, 2018, 卷号: 6
作者:
Song, Jian
;
An, Weijian
;
Wu, Yingwei
;
Tian, Wenxi
收藏
  |  
浏览/下载:13/0
  |  
提交时间:2019/11/19
Cermet fuels
MHD generator
Neutronics
Reactor designs
Space reactors
Thermal hydraulics
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