检索结果-内蒙古大学图书馆

23rd Pacific Basin Nuclear Conference, PBNC 2022

作者： Yanli, Yuan Xianhui, Ye Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China

ISBN: (纸本)9789811987793

Structural dynamic analysis of reactor coolant systems is an important means of evaluating the safety of nuclear power plants under seismic loads. The seismic load distribution of the equipment can be obtained through the dynamic analysis of the reactor coolant system, and the stress of the equipment can be analyzed. In order to reduce the seismic stress of the equipment, effectively reducing the seismic load of the equipment is an important way. In this paper, aiming at the problem of excessive load at the outlet nozzle of the reactor pressure vessel, combined with the design characteristics of the reactor coolant system under the seismic, the optimal design of the reactor coolant system is carried out by the OPTIMUS [1] which is a kind of software developed by Noesis Solutions Company, by which the multidisciplinary analysis processes can be integrated for collaborative optimization design, and ANSYS [2], MATLAB and other software can be integrated to automate the simulation processes. Firstly, a nonlinear model for the dynamic analysis of the reactor coolant system is established, and then the dynamic response sensitivity analysis of the reactor coolant system is carried out, from which the design variables for subsequent optimization analysis are selected, and then the optimization analysis is processed with the force load at the outlet nozzle of the reactor pressure vessel minimized as the target function, and with the force load at the inlet nozzle of the reactor pressure vessel, the bending moment load at the inlet nozzle of the reactor pressure vessel and the bending moment load at the outlet nozzle of the reactor pressure vessel as the state variables. The results show that after the optimization, the load at the outlet nozzle of the reactor pressure vessel is effectively reduced. Relevant optimization analysis methods and analysis processes can be extended to other systems and equipment in the nuclear power plants. © 2023, The Author(s), under exclusive li

关键词： Nozzles

来源：评论

学校读者我要写书评

暂无评论

Effect of Corrosion Damage on Structural Failure Models Under Different Boundry Conditions 23rd

Effect of Corrosion Damage on Structural Failure Models Unde...

引用

23rd Pacific Basin Nuclear Conference, PBNC 2022

作者： Qian, Sheng Sun, Yu Huangfu, Yuzhao Zhang, Ke Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China

ISBN: (纸本)9789811987793

Nuclear energy is an important means to deal with the energy crisis and global climate change, and the long-term safe operation of nuclear power plants strongly depends on the service behavior of structural materials. Nuclear power equipment is subject to complex multiple loads in actual situations, especially under compression, and even the buckling of tiny structures may have important safety hazards. Experience has shown that corrosion is an unavoidable result of nuclear power structures, and structures damaged by corrosion will cause internal stress redistribution under compression, resulting in changes in failure modes. This paper takes the most common uniform corrosion and pitting corrosion as the research objects, and explores the effects of different corrosion forms and corrosion parameters on the buckling failure of compression members under the same corrosion rate. © 2023, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Nuclear fuels

来源：评论

学校读者我要写书评

暂无评论

Prospects for Next Generation Nuclear Power system 23rd

Prospects for Next Generation Nuclear Power System

引用

23rd Pacific Basin Nuclear Conference, PBNC 2022

作者： Zhang, Yaoxiang Yu, Hongxing Xia, Bangyang Li, Wenjie Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9789811988981

systematically research has been carried out on the demand of economic development for low-carbon clean energy and the opportunities faced by the development of nuclear power. A new generation of nuclear power technical index of "Inherent safety, Economics competitiveness, Environment-friendly, and Sustainability" has been formed, which provides guidance for the innovation and development of nuclear power technology. Considering the technical potential of various advanced reactor including the fourth-generation nuclear power system, inherently safe multi-purposed lead-cooled traveling wave reactor is proposed to solve the long-standing problems that have confronted nuclear power. The advanced reactor has attracted much attention because of their unique advantages in fuel supply issue, inherent safety, and economic efficiency. In this study, the main features of the advanced reactors are reviewed and current challenges in their development are pointed out. The advanced reactor obviates the fuel supply issues, including the nuclide enrichment, while making abundant natural uranium usable nuclear fuel. Each of these novel features is technologically separable, so that these new reactor design concepts can be also applied piecewise to enhance prospects in many different utilization circumstances. © 2023, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Nuclear energy

来源：评论

学校读者我要写书评

暂无评论

Research and Application of Endogenous Security Active Defense technology for Domestic Nuclear Safety-Level Gateway Equipment 7th

Research and Application of Endogenous Security Active Defen...

引用

7th International Symposium on Digital Instrumentation and Control technology for Nuclear Power Plant, SICPNPP 2023

作者： Li, Yong Liu, Ming-Xing Peng, Hao Hou, Rong-Bin Ma, Quan Wang, Ru-Qiao Liang, Gen-Hua Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9789819934546

Gateway is a protective equipment at the boundary of the nuclear safety-level I&C system. Aiming at the unknown threat across the boundary of information physical space, this paper studies several key technologies of active defense, and constructs the gateway deep secure architecture that can resist multilevel and multi-dimensional complex attacks. Firstly, the systematic control mechanism of the gateway is constructed, which mechanism includes access control for data flow, IP whitelist at network layer, function code whitelist at application layer, IP/MAC binding and the isolation mechanism of chip’s external ports. Secondly, based on the domestic trust root, the trusted chain from bootloader to the upper-layer application is built to guarantee the secure startup of the embedded system, and the key application processes are measured periodically and verified dynamically during the running process. Based on the above, from building equipment embedded trusted system environment to its security functions, a set of active security defense mechanisms of the gateway equipment sare formed, which enhances the security of the system and improves the information security protection n capability of the equipment. © 2023, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Network security

来源：评论

学校读者我要写书评

暂无评论

SMR FEEDWATER system ANALYSIS 30

SMR FEEDWATER SYSTEM ANALYSIS

引用

30th International Conference on Nuclear Engineering, ICONE 2023

作者： Zhu, Ye Liang, Qiao Xianwei, Liao Zhiyun, Cai Minghao, Liu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China

ISBN: (纸本)9784888982566

The once through steam generator has great heat transfer capacity and compact structure. Some small module reactors (SMR) applied once through steam generatorfor its high thermal efficiency. The thermal hydraulic characteristic of once through steam generator is different from traditional natural cycle steam generator as it doesn't contain water level. Thus the related feed water system is important for the steady operation of the power plant. Base on the thermal hydraulic characteristic of once through steam generator, SMR feed water system that contains process and control model is developed using APROS. The operating parameters are simulated under both different steady states and transient condition. The results show that both the thermal hydraulic and automatic control parameters of SMR feed water system can be simulated accurately in APROS. Reference and guidance can be provided for system optimization and safety analysis. © 2023 by JSME.

关键词： Water levels

来源：评论

学校读者我要写书评

暂无评论

Response Time Analysis Method of Safety-Level DCS in Nuclear Power Plant Based on Probability Theory 1

引用

7th International Symposium on Digital Instrumentation and Control technology for Nuclear Power Plant, SICPNPP 2023

作者： Wen, Jing He, Xian-Jian Chen, Zhao Wan, Zi-Yuan Wu, Zhi-Qiang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610000 China

ISBN: (数字)9789819934553

ISBN: (纸本)9789819934546

Aiming at the incompleteness and inadequacy of the response time analysis method of the current nuclear power plant safety-level digital-control system (DCS), this paper proposes an analysis method based on probability theory for the response time of nuclear power plant safety-level DCS. Firstly, according to the structure and characteristics of the safety-level DCS, the probability model of the response time of the safety-level DCS is established, and the calculation method of the probability distribution of the response time is obtained. Then, according to the obtained calculation method and the parameters of the engineering example, the rang of the response time and the probability density function are calculated, and the response time of the engineering example is simulated, and the simulated response time rang, frequency and probability density function fitting curve are obtained. Finally, the response time of the engineering example is tested by the response time automatic test device, a large amount of data with statistical significance is obtained. After the data is processed, the range, frequency and probability density fitting curve of the response time are obtained. By comparing the theoretical calculation results, simulation results and test results of engineering examples. The correctness and feasibility of the analysis method are verified. © 2023, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Nuclear power plants

来源：评论

学校读者我要写书评

暂无评论

Research on Application of High Temperature and High Pressure Radar Liquid Level Measurement in Nuclear Power Plant 1

引用

7th International Symposium on Digital Instrumentation and Control technology for Nuclear Power Plant, SICPNPP 2023

作者： Deng, Zhi-Guang Zhu, Bi-Wei Wu, Qian Wang, Xue-Mei Xu, Si-Jie Zhu, Jia-Liang Dong, Chen-Long Sun, Yong-Sheng Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (数字)9789819934553

ISBN: (纸本)9789819934546

At present, the water levels of high-temperature and high-pressure vessels such as voltage stabilizers and steam generators on ships' nuclear power plants are measured by the pressure principle. Affected by the load conditions in the vessels, the differential pressure water level measurement has problems of low accuracy and low reliability. The radar type liquid level gauge has the advantages of high precision and high reliability, and is an effective means of measuring the liquid level of high temperature and high pressure containers. In this paper, a FMCW system split guided wave radar based on the principle of frequency domain reflection (FDR) is proposed for liquid level measurement. The antenna probe part and the electronics part adopt a split structure, and the electronics part is installed in the secondary instrument cabin with better environmental conditions., the radar is easy to meet the index requirements of shock, vibration and irradiation. The high-frequency signal emitted by the radar antenna is conducted along the coaxial rod probe, and the signal will be reflected only when it encounters the surface of the material, which effectively eliminates the influence of obstacles such as the heating plate in the container, the internal reference pipe water replenishment device and the reference pipe connection. Non-blind zone measurement of liquid level to meet the liquid level measurement requirements of high temperature and high pressure vessels in ship nuclear power plants. © 2023, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Nuclear power plants

来源：评论

学校读者我要写书评

暂无评论

Research on the Alarm Threshold for Steam Generator Tube Leak Monitoring of Small Modular reactor 23rd

Research on the Alarm Threshold for Steam Generator Tube Lea...

引用

23rd Pacific Basin Nuclear Conference, PBNC 2022

作者： Xia, Ming-ming Wang, Jun-long Xu, Tao Huang, Bo-chen Zhu, Jian-ping Wu, Yi-rui Miao, Jian-xin Chen, Xin Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sicuan Chengdu China

ISBN: (纸本)9789819910229

On the basis of fully learning from the existing principles of leak monitoring alarm thresholds setting of the steam generator tube in pressurized water reactor nuclear power plants, the principle of setting for N-16 leak monitoring alarm thresholds of steam generator tube in small modular reactors is proposed, and the N-16 monitoring alarm thresholds are given. The calculation method for total gamma count rate of steam generator tube leak monitoring alarm thresholds of the small modular reactor is established, and the total gamma count rate under the condition of the leak corresponding to the N-16 monitoring alarm thresholds is calculated to guide the leak monitoring total gamma alarm thresholds set. © 2023, The Author(s).

关键词： Nuclear power plants

来源：评论

学校读者我要写书评

暂无评论

Improving the ductility and toughness of nano-TiC/AZ61 composite by optimizing bimodal grain microstructure via extrusion speed

引用

Journal of Magnesium and Alloys 2024年第8期12卷 3264-3280页

作者： Lingling Fan Mingyang Zhou Wulve Lao Yuwenxi Zhang Hajo Dieringa Ying Zeng Yuanding Huang Gaofeng Quan Key Laboratory of Advanced Technologies of Materials Ministry of EducationChengdu 610031China School of Materials Science and Engineering Southwest Jiaotong UniversityChengdu 610031China Institute of Material and Process Design Helmholtz-Zentrum HereonGeesthacht 21502Germany Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu 610213China School of Civil Engineering Southwest Jiaotong UniversityChengdu 610031China Institute of Metallic Biomaterials Helmholtz-Zentrum HereonGeesthacht 21502Germany

In this study,the nano-TiC/AZ61 composites with different heterogeneous bimodal grain(HBG)structures and uniform structure are obtained by regulating the extrusion *** effect of HBG structure on the mechanical properties of the composites is *** increasing ductility and toughening mechanism of HBG magnesium matrix composites are carefully *** the extrusion speed increases from 0.75 mm/s to 2.5 mm/s or 3.5 mm/s,the microstructure transforms from uniform to HBG *** with Uniform-0.75 mm/s composite,Heterogeneous-3.5 mm/s composite achieves a 116.7%increase in ductility in the plastic deformation stage and almost no reduction in ultimate tensile *** is mainly because the lower plastic deformation inhomogeneity and higher strain hardening due to hetero-deformation induced(HDI)***,Heterogeneous-3.5 mm/s composite achieves a 108.3%increase in toughness compared with the Uniform-0.75 mm/s *** is mainly because coarse grain(CG)bands can capture and blunt cracks,thereby increasing the energy dissipation for crack propagation and improving *** addition,the CG band of the Heterogeneous-3.5 mm/s composite with larger grain size and lower dislocation density is more conducive to obtaining higher strain hardening and superior blunting crack ***,the increased ductility and toughness of the Heterogeneous-3.5 mm/s composite is more significant than that Heterogeneous-2.5 mm/s composite.

关键词： Nano-TiC/AZ61 composite Extrusion speed Heterogeneous bimodal grain structure Increasing ductility mechanism Toughening mechanism

来源：评论

学校读者我要写书评

暂无评论

Openfoam Simulation of Damping Controlled Fluidelastic Instability 23rd

Openfoam Simulation of Damping Controlled Fluidelastic Insta...

引用

23rd Pacific Basin Nuclear Conference, PBNC 2022

作者： Feng, Zhipeng Liu, Shuai Qi, Huanhuan Huang, Xuan Lv, Xi Science and Technology On Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China

ISBN: (纸本)9789811987793

A parallel triangular tube bundle with a single flexible tube is taken as the object, and the most dangerous mechanism of flow induced vibration in the tube bundle structure, fluidelastic instability (FEI) is studied based on the open-source CFD tool OpenFOAM. Firstly, a numerical model describing the fluid-structure interaction of the tube bundle is established by combining computational fluid dynamics with the vibration equation of the tube;Then, the variation of lift coefficient, drag coefficient, lateral displacement and lift spectrum with velocity is discussed. The results show that the open-source tool OpenFOAM can be easily used to predict the fluidelastic instability of tube bundle. © 2023, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Computational fluid dynamics

来源：评论

学校读者我要写书评

暂无评论

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：

请选择收藏分类：

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

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：