中国科学院机构知识库网格
Chinese Academy of Sciences Institutional Repositories Grid
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CAS IR Grid
机构
上海应用物理研究所 [4]
合肥物质科学研究院 [2]
力学研究所 [1]
金属研究所 [1]
采集方式
OAI收割 [8]
内容类型
期刊论文 [8]
发表日期
2025 [1]
2021 [1]
2020 [1]
2019 [1]
2018 [2]
2017 [1]
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Dynamic analysis of a large-scale fast reactor core under seismic condition
期刊论文
OAI收割
NUCLEAR ENGINEERING AND DESIGN, 2025, 卷号: 432, 页码: 14
作者:
Liu BS(刘宝收)
;
Peng Q(彭庆)
;
Liu XM(刘小明)
  |  
收藏
  |  
浏览/下载:7/0
  |  
提交时间:2025/02/17
Reactor core
Nonlinear contact
Modal superposition method
Seismic analysis
Recent Progress in Modeling of CFETR Plasma Profiles from Core to Edge
期刊论文
OAI收割
JOURNAL OF FUSION ENERGY, 2021, 卷号: 40
作者:
Chen, Jiale
;
Jia, Guozhang
;
Xiang, Nong
  |  
收藏
  |  
浏览/下载:36/0
  |  
提交时间:2021/05/10
CFETR
Integrated modeling
Scenario development
Coupling between core and edge
Tokamak reactor
Numerical simulation of stress behavior of dowel-brick structures in TMSR
期刊论文
OAI收割
NUCLEAR SCIENCE AND TECHNIQUES, 2020, 卷号: 31, 期号: 5, 页码: -
作者:
Fan, HQ
;
Huang, CC
;
Wang, X
;
Tsang, DKL
;
Zhang, XC
  |  
收藏
  |  
浏览/下载:26/0
  |  
提交时间:2021/09/06
CORE-BOTTOM STRUCTURE
ASEISMIC INTEGRITY
SEISMIC RESPONSE
REACTOR
Computational- and experimental-based analysis of the load capacity of dowel-brick structure of graphite component in TMSR
期刊论文
OAI收割
NUCLEAR ENGINEERING AND DESIGN, 2019, 卷号: 355, 页码: -
作者:
Fan, HQ
;
Huang, CC
;
Zhang, XC
;
Wang, XY
;
Zhu, SF
  |  
收藏
  |  
浏览/下载:24/0
  |  
提交时间:2020/10/16
CORE-BOTTOM STRUCTURE
ASEISMIC INTEGRITY
BEHAVIOR
REACTOR
Numerical investigation of the core outlet temperature fluctuation for the lead-based reactor
期刊论文
OAI收割
ANNALS OF NUCLEAR ENERGY, 2018, 卷号: 117, 期号: 无, 页码: 194-201
作者:
Wang, Lizhi
;
Wu, Guowei
;
Wang, Jin
;
Jin, Ming
;
Song, Yong
  |  
收藏
  |  
浏览/下载:19/0
  |  
提交时间:2019/08/23
Temperature fluctuation
Lead-based reactor
Core outlet
Development and application of optimal burnup estimation methodology for pebble bed reactor
期刊论文
OAI收割
ANNALS OF NUCLEAR ENERGY, 2018, 卷号: 117, 页码: 343-349
作者:
Tang, HB
;
Han, JL
;
Li, XX
;
Zou, CY
  |  
收藏
  |  
浏览/下载:16/0
  |  
提交时间:2018/09/06
High-temperature Reactor
Fuel-management Code
Thorium
Core
Design
Flow effect on I-135 and Xe-135 evolution behavior in a molten salt reactor
期刊论文
OAI收割
NUCLEAR ENGINEERING AND DESIGN, 2017, 卷号: 314, 页码: 318-325
作者:
Wu, JH
;
Guo, C
;
Cai, XZ
;
Yu, CG
;
Zou, CY
  |  
收藏
  |  
浏览/下载:22/0
  |  
提交时间:2017/12/08
Molten Salt Reactor
Core Burnup
Flow Effect
Remaining life prediction of the core shroud due to stress corrosion cracking failure in BWRs using numerical simulations
期刊论文
OAI收割
Journal of Nuclear Science and Technology, 2015, 卷号: 52, 期号: 1, 页码: 96-103
Y. K.
;
Lu Li, S. P.
;
Li, D. Z.
;
Kaji, Y.
收藏
  |  
浏览/下载:14/0
  |  
提交时间:2015/05/08
stress corrosion cracking
boiling water reactor
life prediction
316L
stainless steel
finite element methods
core shroud