检索结果-内蒙古大学图书馆

您好，读者！请登录

内蒙古大学图书馆

首页
概况
党建
资源
服务
科研支持
- 论文收录引用证明
- 科技查新
知识产权
档案馆
帮助

咨询与建议

建议与咨询留下您的常用邮箱和电话号码，以便我们向您反馈解决方案和替代方法

您的常用邮箱：*

您的手机号码：*

问题描述：

当前已输入0个字，您还可以输入200个字

全部搜索
期刊论文
图书
学位论文
标准
纸本馆藏
外文资源发现
数据库导航
超星发现

高级检索

时间限定

出版年份：

文献类型

图书期刊文献学位论文多媒体

馆藏选择

电子馆藏纸本馆藏

核心期刊

全部期刊 SCI 收录期刊 SSCI 收录期刊 EI 收录期刊 CSCD 收录期刊 CSSCI 收录期刊

语言

中文英文

文献类型

期刊文献图书学位论文标准纸本馆藏

帮助

文字说明：

T=题名（书名、题名），A=作者（责任者），K=主题词，P=出版物名称，PU=出版社名称，O=机构（作者单位、学位授予单位、专利申请人），L=中图分类号，C=学科分类号，U=全部字段，Y=年（出版发行年、学位年度、标准发布年）

检索规则说明：

AND代表“并且”；OR代表“或者”；NOT代表“不包含”；(注意必须大写,运算符两边需空一格)

检索范例：

范例一：(K=图书馆学 OR K=情报学) AND A=范并思 AND Y=1982-2016
范例二：P=计算机应用与软件 AND (U=C++ OR U=Basic) NOT K=Visual AND Y=2011-2016

分类表

所选分类

>> <<

限定检索结果

文献类型

411 篇 会议
215 篇 期刊文献

馆藏范围

626 篇 电子文献
0 种 纸本馆藏

日期分布

学科分类号

552 篇 工学
- 284 篇 动力工程及工程热...
- 240 篇 核科学与技术
- 173 篇 力学（可授工学、理...
- 155 篇 计算机科学与技术...
- 143 篇 软件工程
- 137 篇 化学工程与技术
- 131 篇 安全科学与工程
- 104 篇 机械工程
- 90 篇 材料科学与工程（可...
- 86 篇 冶金工程
- 58 篇 控制科学与工程
- 42 篇 电气工程
- 40 篇 交通运输工程
- 34 篇 土木工程
- 30 篇 仪器科学与技术
- 20 篇 信息与通信工程
- 19 篇 电子科学与技术（可...
- 18 篇 生物工程
- 11 篇 石油与天然气工程
- 10 篇 建筑学
430 篇 理学
- 246 篇 物理学
- 162 篇 化学
- 155 篇 数学
- 47 篇 统计学（可授理学、...
- 21 篇 生物学
- 16 篇 系统科学
- 9 篇 地球物理学
69 篇 管理学
- 63 篇 管理科学与工程(可...
7 篇 经济学
5 篇 法学
3 篇 农学
3 篇 医学
2 篇 教育学
1 篇 文学
1 篇 艺术学

主题

33 篇 nuclear power pl...
11 篇 finite element m...
9 篇 silicon carbide
9 篇 heat transfer
8 篇 two phase flow
8 篇 heat flux
7 篇 pressurized wate...
7 篇 sensitivity anal...
6 篇 computational fl...
6 篇 steam generators
6 篇 loss of coolant ...
5 篇 failure analysis
5 篇 nuclear fuels
5 篇 liquid metals
5 篇 condensation
5 篇 digital control ...
5 篇 grain boundaries
5 篇 numerical method...
4 篇 uranium dioxide
4 篇 coolants

机构

411 篇 science and tech...
57 篇 science and tech...
37 篇 department of en...
30 篇 nuclear power in...
25 篇 nuclear power in...
11 篇 key laboratory o...
11 篇 fundamental scie...
11 篇 school of nuclea...
9 篇 national key lab...
8 篇 college of nucle...
8 篇 key laboratory o...
8 篇 school of nuclea...
6 篇 harbin engineeri...
6 篇 state key labora...
6 篇 science and tech...
6 篇 national key lab...
5 篇 cnnc key laborat...
5 篇 state key labora...
5 篇 college of energ...
5 篇 college of physi...

作者

39 篇 deng jian
23 篇 wang kan
23 篇 li qing
22 篇 yu hongxing
15 篇 peng xingjie
15 篇 qiu suizheng
14 篇 tian wenxi
13 篇 yao dong
13 篇 su guanghui
12 篇 huang shanfang
12 篇 gong helin
12 篇 chen ping
12 篇 chai xiaoming
11 篇 yu yingrui
11 篇 chen zhi
11 篇 zhang xu
11 篇 ma yugao
10 篇 bai xiaoming
10 篇 qiu zhifang
10 篇 deng zhi-guang

语言

591 篇 英文
20 篇 中文
11 篇 其他
1 篇 法文

检索条件"机构=Science and Technology on Reactor System Design"

共 626 条记录，以下是361-370 订阅

全选清除本页清除全部题录导出标记到"检索档案"

详细简洁

排序：

Semantic Segmentation of Substation Scenes Using Attention-Based Model 4

Semantic Segmentation of Substation Scenes Using Attention-B...

引用

4th IEEE International Conference on Electronics technology, ICET 2021

作者： Chen, Qian Zhang, Changhua Li, Hao Wan, Naijia Wang, Donghui Xu, Bin University of Electronic Science and Technology of China School of Information and Software Engineering Chengdu China University of Electronic Science and Technology of China School of Mechanical and Electrical Engineering Chengdu China Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory Chengdu China

ISBN: (纸本)9781728176734

Inspection robots are widely used in transformer substation for inspection tasks. In order to complete the task, the robots need to understand and recognize road scenes. However, the transformer substation contains lots of similar and small equipment, which are difficult to recognize. To address this problem, we propose a semantic segmentation model to recognize road scenes. Specifically, our proposed model discriminates the equipment by leveraging multi-view method. We use attention mechanism to strengthen the relationship between pixels that belong to an individual category. Compared with previous methods, our approach achieves a good performance in a new dataset from a transformer substation and shows robustness in recognizing equipment of transformer substation. © 2021 IEEE.

关键词： Roads and streets

来源：评论

学校读者我要写书评

暂无评论

Study on control strategy of hydrogen risk in small containment under severe accident 26

Study on control strategy of hydrogen risk in small containm...

引用

2018 26th International Conference on Nuclear Engineering, ICONE 2018

作者： Zou, Zhiqiang Hou, Liqiang Zhang, Ming Deng, Chunrui Peng, Huanhuan Xuedong, Qiao Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China Nuclear and Radiation Safety Center Ministry of Environment Protection of P.R.China Beijing China

ISBN: (纸本)9780791851517

Hydrogen combustion or detonation happened in the containment within the process of the small reactor severe accident may threaten the integrity of the containment. In this paper, based on systemic design of the Small Modular reactor (SMR) surrounded by the steel containment, an innovatory combustible gas control strategy which using the passive containment cooling system (PCCS) and passive autocatalytic recombiners (PARs) is made to control the hydrogen risk in the small steel containment. A severe accident hydrogen risk analysis model is built by the integrative severe accident analysis program MELCOR, the validity of the strategy is analyzed at a typical severe accident. With this understanding, a three-dimensional computed fluid dynamics hydrogen behavior analysis model of the small steel containment is established by GASFLOW code, and the gas distribution non-uniformity in the containment is analyzed. The result shows that the steam condensation process in the containment could be slowed down by controlling the action of PCCS, and the steam concentration in the containment could be in the range of high level, while the oxygen concentration could be in the range of low level. If the PARs were added, the PARs could consume the hydrogen and oxygen in the containment sustainedly. The containment atmosphere could be in an inerted condition during the accident process, even though the hydrogen concentration in the containment is high. The gas distribution non-uniformity analysis result shows that oxygen concentration was low in the extent of high hydrogen concentration and high steam concentration, the steam, oxygen and hydrogen distribution non-uniformity would not affect the inerted atmosphere of containment. Copyright © 2018 ASME.

关键词： Risk analysis

来源：评论

学校读者我要写书评

暂无评论

reactor Containment Passive Safety Analysis: Steam Condensation in Presence of Non-condensable Gas Scaled Experiment and Modeling

Reactor Containment Passive Safety Analysis: Steam Condensat...

引用

2024 Pacific Basin Nuclear Conference, PBNC 2024

作者： Bhowmik, Palash K. Schlegel, Joshua P. Sabharwall, Piyush Division of Reactor System Design and Analysis Idaho National Laboratory Idaho FallsID United States Department of Nuclear Engineering and Radiation Science Missouri University of Science and Technology RollaMO United States

ISBN: (纸本)9798331307653

This study presents steam condensation scaled experiments and semi-empirical models in presence of nitrogen (N)—a noncondensable gas (NCG), simulating air in the reactor containment—to support water-cooled small modular reactors (SMRs) passive containment cooling system (PCCS) design and analysis. Previous experimental studies on PCCS are focused on fixed and smaller tube (mostly 2-in.) geometries and specific test condition variations, bringing challenges with geometric scaling and mismatching with SMR prototypic design. To address these challenges, this study presents steam condensation test dataset obtained from three scaled test sections of 1-, 2-, and 4-in.-diameter steam condensers with an annular/ jacket cooling of 2-, 3-, and 6 in.-diameter tubes, respectively. Test data were collected for steam ranges from 58 to 63 kg/hr., and NCG flow of to 13.3 kg/hr. Annular cooling water flow was varied to obtain required testing conditions of saturated steam 4.4 inlet and fully condensed outlet. Axial temperature test data of bulk cooling water, steam and condensate were collected by thermocouples for three test sections and various steam-NCG mixing/testing conditions. A standard data reduction method was adopted—utilizing iterative and nodalized mass and heat transfer calculation—to estimate axial local heat fluxes, heat transfer coefficients (HTCs), condensation rates, film thickness, and Nusselt number. Based on the obtained dataset semi-empirical model results—a ratio of experimental and Nusselt’s theoretical HTC are presented. Such results and findings are supportive of developing scaled-up testing facility, to model validations and accelerate next generation of reactors development and deployment. © 2024 Pacific Basin Nuclear Conference, PBNC 2024. All rights reserved.

关键词： Thermocouples

来源：评论

学校读者我要写书评

暂无评论

Microstructure and mechanical properties of tib2/ al-si composites fabricated by electron beam rapid manufacture 21st

Microstructure and mechanical properties of tib2/ al-si comp...

引用

21st Chinese Materials Conference, CMC 2020

作者： Yang, Qingfeng Xia, Cunjuan Li, Xianfeng Wang, Haowei Liao, Nan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China The State Key Laboratory of Metal Matrix Composites Shanghai Jiaotong University Shanghai200240 China

ISBN: (纸本)9783035717389

Bulky sample was fabricated by electron beam rapid manufacture (EBRM) technology, in which Ф1.6 mm wire of in-situ TiB2/Al-Si compositeswas selected as deposition metal, following byT6 heat treatment. The microstructure and mechanical properties of the bulky sample before and afterheat treatment were analyzed. Experimental results showed that the microstructure parallel to the weld was similar to that perpendicular to the weld. The microstructure of the as-deposited sample consisted of columnar and equiaxed grains, in which siliconwas distributed along the grain boundary and the grain size was about 30 μm. Besides, some TiB2 particles converged at the grain boundary. After T6 heat treatment, the average grain size of the sample *** average hardness of the sample was increased to 114.65 HV from 46.55 HV, an increase of 146%. The tensile strength of the sample increased to 326.66MPafrom 143.97 MPa, but the elongationdecreased compared with that of the as-deposited state. The tensile test showed that the mechanical properties of TiB2/Al-Si composites formed by electron beam rapid manufacture were isotropic before and after heat treatment. © 2021 Trans Tech Publications Ltd, Switzerland.

关键词： Electron beams

来源：评论

学校读者我要写书评

暂无评论

Multi-physics Coupling Analyses of Nuclear Thermal Propulsion reactor 23rd

Multi-physics Coupling Analyses of Nuclear Thermal Propulsio...

引用

23rd Pacific Basin Nuclear Conference, PBNC 2022

作者： Han, Wenbin Guan, Zechuan Huang, Shanfang Deng, Jian Department of Engineering Physics Tsinghua University Beijing China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China China Institute of Atomic Energy Beijing China

ISBN: (纸本)9789819910229

Nuclear thermal propulsion (NTP) reactors have high-temperature solid-state characteristics and significant thermal expansion, which therefore require multi-physics coupling analyses. In this paper, the framework of Neutronics, Thermal-Hydraulics and Mechanics coupling (N/T-H/M) of nuclear thermal propulsion reactor is developed, and the typical reactor XE-2 is analyzed with this method. The results show that the N/T-H/M coupling will bring -1049 pcm negative reactivity, of which the thermal expansion effect accounts for 22%, indicating that the nuclear thermal propulsion reactor has a certain capacity for self-regulation. However, thermal expansion will lead to 0.88 mm peak deformation and 233 MPa peak stress, which will severely threaten the mechanical tolerance of the materials. Therefore, there is a trade-off between the advantages and disadvantages of the high-temperature solid-state core while designing NTP reactors. © 2023, The Author(s).

关键词： Thermal expansion

来源：评论

学校读者我要写书评

暂无评论

DEVELOPMENT OF QUENCH ANALYSIS PROGRAM BASED ON ARSAC 29

DEVELOPMENT OF QUENCH ANALYSIS PROGRAM BASED ON ARSAC

引用

2022 29th International Conference on Nuclear Engineering, ICONE 2022

作者： Zhong, Lei Yu, Hongxing Chen, Deqi Liu, Hanzhou Deng, Jian Wu, Dan Science and Technology on Reactor System Design Technology Laboratory Sichuan Chengdu610041 China Key Laboratory of Low-grade Energy Utilization Technologies and Systems Chongqing University Ministry of Education Chongqing400044 China

ISBN: (纸本)9780791886410

ARSAC is a reactor system analysis program independently developed in China. In this paper, a quench analysis module is developed based on ARSAC program. The boiling curve suitable for quench process is established and several classical minimum film boiling temperature and models are implanted. The new program can reflect the influence of minimum film boiling temperature and heat transfer models on the quench process, thus it can be used to estimate the effect of surface oxidation and different cladding materials on the quenching process. The calculation results of the new program are in good agreement with the experimental data, and can better simulate the quench process of fuel element under LOCA. Copyright © 2022 by ASME.

关键词： Heat transfer

来源：评论

学校读者我要写书评

暂无评论

Development of self-healing coating on fuel cladding for water-cooling nuclear reactors 14

Development of self-healing coating on fuel cladding for wat...

引用

14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water reactor Fuel Performance Conference, TOP FUEL 2019

作者： Duan, Z.G. Xin, G.S. Zhou, Y. Li, Y.M. Abe, H. Yang, H.L. Kano, S. McGrady, J. Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China Nuclear Professional School School of Engineering University of Tokyo Tokai Ibaraki319-1188 Japan

A novel scheme for a bilayer coating with self-healing ability is proposed in this study. The candidate materials for the coatings and the potential self-healing reaction are assessed in high-temperature aqueous environments and high-temperature air. The pure Cr2O3 layer and the composite of Cr2O3 and MoO3 are the candidate materials for the outer layer and inner layer, respectively, due to their compatibility under normal condition. Fe2O3-MoO3 reactions exhibit a potential ability to heal the cracks because of a high reaction rate under normal condition. Copyright © GLOBAL 2019 - International Nuclear Fuel Cycle Conference and TOP FUEL 2019 - Light Water reactor Fuel Performance *** rights reserved.

关键词： Light water reactors

来源：评论

学校读者我要写书评

暂无评论

Stratification and heat transfer of molten corium pool for in-vessel retention

Stratification and heat transfer of molten corium pool for i...

引用

2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference

作者： Xiang, Qingan Deng, Jian Zhu, Dahuan Wu, Xiaoli Bi, Jinsheng Chen, Baowen Cai, Rong Qian, Libo YugaoMa Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China Nuclear and radiation safety center Ministry of Environment Protection of P.R. China Beijing China

ISBN: (纸本)9780791883778

In-vessel retention (IVR) consists in cooling the molten corium contained in the lower head of reactor vessel by natural convection and reactor cavity flooding. The general approach which is used to study IVR problems is a "bounding" approach which consists in assuming a specified corium pool stratification in the vessel and then demonstrating that the vessel can cope with the resulting thermal and mechanical loads. Thermal loading on the vessel is controlled by the convective heat transfer inside the molten corium pool. Traditionally molten corium pool in the lower head was expected to stratify into two-layer with the dense oxide pool at the bottom and the light metal layer on the top. Based on the MASCA experiments, the increased density of the metal layer attributed to a transfer of uranium metal leads to inverse stratification with a heavy metal layer relocating below the oxide pool. This behavior can be explained by physicochemical interaction between the oxidic and metallic phases of the corium pool. Therefore, a methodology which couples physicochemical effects and thermal hydraulics has been developed to address the IVR issue. The main purpose of this paper is to present this methodology and its application for calculate stratification probability of two-layer and three-layer configuration, analyze the safety margin of IVR in two-layer and three-layer configuration, and evaluate the lower head heat thermal failure probability. Copyright © 2020 ASME

关键词： Heat flux

来源：评论

学校读者我要写书评

暂无评论

Disorders in fluid filled pipeline structure with elastic helmholtz resonators 29

Disorders in fluid filled pipeline structure with elastic he...

引用

2022 29th International Conference on Nuclear Engineering, ICONE 2022

作者： Zeng, Qingna Wang, Donghui Zang, Fenggang Zhang, Yixiong Wang, Bihao Yuan, Zhihao Science and Technology on Reactor System Design Technology Laboratory Chengdu610213 China Nuclear Power Institute of China Chengdu610213 China College of Shipbuilding Engineering Harbin Engineering University Harbin150001 China

ISBN: (纸本)9780791886359

This paper studies the influence of hybrid disorders on acoustic transmission characteristic in pipeline with periodic elastic HRs. Band gap structures (BGs) for infinite period are investigated by transfer matrix method and finite element method respectively, and fit well with the corresponding transmission loss (TL) for finite regular periods. By introducing a certain degree of uncertainty level, Interval analysis method is used to convert uncertain parameter problems into two deterministic models. Frequency response function (FRF) for near-periodic structure with single disorder and BGs for quasiperiodic structure with multiple disorders considering cavity radius and periodic length are investigated. The existence of disorders in periodic structure would always reduce attenuation interval and intensity, some disturbance would even change the original acoustic transmission characteristic and excite completely new attenuation zones. The sensitivity of pipeline acoustic vibration transfer characteristic to disorder parameter depends on attenuation mechanism, as for periodic elastic HRs pipeline, acoustic propagation stability is more sensitive to characteristic of locally resonant unit. The work in this paper enriches the stability analysis of pipeline with elastic HRs, which would provide theoretical reference for noise and vibration reduction design in practical engineering applications. © 2022 American Society of Mechanical Engineers (ASME). All rights reserved.

关键词： Transfer matrix method

来源：评论

学校读者我要写书评

暂无评论

Research and Application of Nuclear reactor Computational Data Framework Based on HDF5 7th

Research and Application of Nuclear Reactor Computational Da...

引用

7th International Conference on Artificial Intelligence and Security, ICAIS 2021

作者： Lu, Wei Feng, Jintao Yang, Hao Zeng, Hui Pan, Junjie Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China School of Computer Science Chengdu University of Information Technology Chengdu610225 China School of Information and Software Engineering University of Electronic Science and Technology of China Chengdu610054 China

ISBN: (纸本)9783030786175

Nuclear reactor computing software need to process and maintain complex and massive data sets. In order to meet the requirement of mass data storage and processing in software, the data storage model and I/O method and programming interface of HDF5 (Hierarchical Data Format v5) are deeply studied. According to the data storage and processing requirement of typical nuclear reactor computing data such as assembly or core neutronics computing data and core thermal-hydraulic computing data, RCDF-H5 (reactor Compute Data Framework based on HDF5) is proposed. KYMRES (KYlin-2 Main RESults databank) and COMRES (COre Main RESults databank) are designed and implemented based on RCDF-H5. The performance tests show that RCDF-H5 has a higher I/O efficiency than conventional storage solutions. A new data storage and management solution for nuclear reactor computing software is provided. © 2021, Springer Nature Switzerland AG.

关键词： Digital storage

来源：评论

学校读者我要写书评

暂无评论

没有更多数据了...

全选清除本页清除全部题录导出标记到“检索档案”

共63页 << < 33 34 35 36 37 38 39 40 41 42 > >>

检索报告对象比较合并检索0

隐藏清空

合并搜索

回到顶部

执行限定条件

内容：

评分：

请选择保存的检索档案：

请选择收藏分类：

订阅名称：

通借通还

温馨提示：

图书名称：

借书校区：

取书校区：

手机号码：

邮箱地址：

一卡通帐号：

电话和邮箱必须正确填写，我们会与您联系确认。

联系人：

所在院系：

联系邮箱：

联系电话：

内蒙古自治区呼和浩特市赛罕区大学西街235号邮编: 010021

建议与咨询 留下您的常用邮箱和电话号码，以便我们向您反馈解决方案和替代方法

时间限定

文献类型

馆藏选择

核心期刊

语言

文献类型

帮助

文字说明：

检索规则说明：

检索范例：

分类表

所选分类

限定检索结果

文献类型

馆藏范围

日期分布

学科分类号

主题

机构

作者

语言

请选择保存的检索档案： 新增检索档案 确定 取消

请选择收藏分类： 新增自定义分类 确定 取消

通借通还

建议与咨询留下您的常用邮箱和电话号码，以便我们向您反馈解决方案和替代方法

请选择保存的检索档案：

请选择收藏分类：