×
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
西安交通大学 [13]
内容类型
期刊论文 [7]
会议论文 [6]
发表日期
2019 [1]
2018 [1]
2017 [1]
2016 [2]
2015 [4]
2014 [4]
更多...
×
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13条,第1-10条
帮助
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
Investigation on the critical heat flux in a 2 by 2 fuel assembly under low flow rate and high pressure with a CFD methodology
期刊论文
Annals of Nuclear Energy, 2019, 卷号: 124, 页码: 69-79
作者:
Zhang, Rui
;
Duarte, Juliana P.
;
Cong, Tenglong
;
Corradini, Michael L.
收藏
  |  
浏览/下载:16/0
  |  
提交时间:2019/11/19
Boiling models
CFD methodologies
Critical heat flux(CHF)
Flow regime transition
Small modular reactors
Temperature increase
Two phase
University of Wisconsin - Madison
Iron–Chromium–Aluminum (FeCrAl) cladding oxidation kinetics and auxiliary feedwater sensitivity analysis—Short-Term station blackout simulation of surry nuclear power plant
会议论文
作者:
Wang, Jun
;
Mccabe, Mckinleigh
;
Haskin, Troy Christopher
;
Wu, Yingwei
;
Su, Guanghui
收藏
  |  
浏览/下载:3/0
  |  
提交时间:2019/11/19
Constant injection
FeCrAl cladding
ORNL oxidation kinetic
Steam generator auxiliary feedwater
Water level control
ACCIDENT TOLERANCE CLADDING THERMAL HYDRAULIC SIMULATION AND OXIDATION KINETIC SENSITIVITY ANALYSIS
会议论文
作者:
Wang, Jun
;
Mccabe, Mckinleigh
;
Haskin, Troy Christopher
;
Wu, Yingwei
;
Su, Guanghui
收藏
  |  
浏览/下载:4/0
  |  
提交时间:2019/11/26
The development of candling module code in module in-vessel degraded analysis code MIDAC and the relevant calculation for CPR1000 during large-break LOCA
期刊论文
Journal of Nuclear Engineering and Radiation Science, 2016, 卷号: 2, 期号: [db:dc_citation_issue]
作者:
Wang, Jun
;
Fan, Yuqiao
;
Zhang, Yapei
;
Ni, Xinghe
;
Tian, Wenxi
收藏
  |  
浏览/下载:4/0
  |  
提交时间:2019/12/02
CPR1000
LOCA
MAAP
MIDAC
Severe accident
PHEBUS FPT-1 simulation by using MELCOR and primary blockage model exploration
期刊论文
NUCLEAR ENGINEERING AND DESIGN, 2016, 卷号: 307, 页码: 119-129
作者:
Wang, Jun
;
Wang, Chen
;
Corradini, Michael L.
;
Haskin, Troy
;
Tian, Wenxi
收藏
  |  
浏览/下载:6/0
  |  
提交时间:2019/11/26
Core degradation research and the simulation of PHEBUS FPT-1
会议论文
作者:
Wang, Jun
;
Corradini, Michael L.
;
Haskin, Troy
收藏
  |  
浏览/下载:2/0
  |  
提交时间:2019/12/02
Simulation of the PHEBUS FPT-1 experiment using MELCOR and exploration of the primary core degradation mechanism
期刊论文
ANNALS OF NUCLEAR ENERGY, 2015, 卷号: 85, 期号: [db:dc_citation_issue], 页码: 193-204
作者:
Wang, Jun
;
Corradini, Michael L.
;
Fu, Wen
;
Haskin, Troy
;
Zhang, Yapei
收藏
  |  
浏览/下载:2/0
  |  
提交时间:2019/12/02
Core degradation
MELCOR
PHEBUS FPT1
Development of cladding oxidation analysis code [COAC] and application for early stage severe accident simulation of AP1000
期刊论文
PROGRESS IN NUCLEAR ENERGY, 2015, 卷号: 85, 期号: [db:dc_citation_issue], 页码: 352-365
作者:
Mao, Keyou
;
Wang, Jun
;
Li, Longze
;
Zhang, Yapei
;
Tian, Wenxi
收藏
  |  
浏览/下载:2/0
  |  
提交时间:2019/12/02
Hydrogen generation rate
AP1000
COAC
Clad solid-phase oxidation models
COMPARISON OF HYDROGEN GENERATION RATE BETWEEN CORA-13 TEST AND MELCOR SIMULATION: CLAD SOLID-PHASE OXIDATION MODELS USING SELF-DEVELOPED CODE MYCOAC
期刊论文
NUCLEAR TECHNOLOGY, 2015, 卷号: 192, 期号: [db:dc_citation_issue], 页码: 25-34
作者:
Wang, Jun
;
Corradini, Michael L.
;
Haskin, Troy
;
Zhang, Yapei
;
Lu, Qing
收藏
  |  
浏览/下载:6/0
  |  
提交时间:2019/12/02
hydrogen generation rate
gaseous diffusion model
clad solid-phase oxidation model
Development of the code COAC for oxidation during core melting
会议论文
作者:
Mao, Keyou
;
Zhang, Yapei
;
Corradini, Michael L.
收藏
  |  
浏览/下载:1/0
  |  
提交时间:2019/12/02
©版权所有 ©2017 CSpace - Powered by
CSpace