检索结果-内蒙古大学图书馆

Research and design on the Control Rod Drive Mechanism Power Supply and Control Strategy for the Nuclear Power Plants Based on Silicon-Controlled Rectifier

Research and Design on the Control Rod Drive Mechanism Power...

引用

International Conference on Power Electronics and Motion Control (IPEMC)

作者： A. Mingzhou Xu B. Gao Zheng C. Zerun Zhao D. Ping Yang E. Yusheng Peng Science and Technology on Reactor System Design Technology Laboratory China Southwest Jiaotong University China

ISBN: (数字)9798350351330

ISBN: (纸本)9798350351347

Due to the characteristics of large output current ripple and long current rise and fall times in the current rod control power supply basedsilicon-controlled rectifier, a decoupling nonlinear adaptive control is *** proposed control strategy can improve the rod control power supply of the speed of respond and the steady-state current accuracy. Practical application has shown that this method solves the output current ripple and the rise and fall time of the current, meeting the working requirements of rod control power supply in nuclear power plants.

关键词： Accuracy Power supplies Conferences Asia Rectifiers Power electronics Steady-state

来源：评论

学校读者我要写书评

暂无评论

Improving the ductility of laser directed energy deposited borated stainless steel by increasing laser power

引用

Journal of Manufacturing Processes 2025年 145卷 494-507页

作者： Huang, Sheng Li, Qingyu Zhang, Xiaoyu Cui, Bin Li, Dichen Zhang, Anfeng Miao, Kai State Key Laboratory for Manufacturing Systems Engineering School of Mechanical Engineering Xi'an Jiaotong University Xi'an710049 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China Department of Mechanical and Electrical Engineering Yuncheng University Yuncheng044000 China Co. Ltd. Chengdu610091 China

Borated stainless steels (BSSs) are extensively applied in the nuclear energy industry due to boron's excellent thermal neutron absorption capacity, but large and brittle borides formed during casting result in a low ductility. Here, a BSS was produced by laser directed energy deposition, and an investigation was conducted to analyze the impact of laser power on both the microstructure and mechanical properties of the deposited material. Fibrous borides with relatively low volume fraction in the overlapping zone resulted in higher ductility, while lamellar borides with relatively large volume fraction in the non-overlapping zone led to higher strength. As the laser power increased from 180 W to 330 W, the size of fibrous and lamellar eutectic borides and austenite increased significantly, the width of the soft overlapping zone increased by 2.27 times, and the elongation increased by 2.03 times, although yield strength and ultimate tensile strength decreased by 46.3 % and 31.7 %, respectively. As a result, these findings confirmed the feasibility of significantly improving the ductility of the as-deposited BSS by increasing the laser power. The work here provides a way to tailoring the mechanical properties of BSS produced by laser additive manufacturing. © 2025 The Society of Manufacturing Engineers

关键词： Ductility

来源：评论

学校读者我要写书评

暂无评论

Direct Contact Condensation Characteristics of Steam Injection into Cold-Water Pipe Under Rolling Condition 23rd

Direct Contact Condensation Characteristics of Steam Injecti...

引用

23rd Pacific Basin Nuclear Conference, PBNC 2022

作者： Wang, Zhiwei He, Yanping Duan, Zhongdi Huang, Chao Liu, Shiwen State Key Laboratory of Ocean Engineering Shanghai Jiao Tong University Shanghai China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9789819910229

Direct contact condensation (DCC) is widely occurred in nuclear power systems and leads to undesired phenomena such as condensation-induced water hammer. For ocean nuclear power ships, DCC is inevitable in the passive heat removal system and influenced by sea conditions. In this paper, the characteristics of DCC under rolling conditions are analyzed. The numerical model of DCC is established based on computational fluid dynamics approach. The VOF model, SST k–ω turbulence model and the additional inertia force model are incorporated to describe the liquid-gas two-phase flow under the rolling motion. The condensation model based on surface renewal theory (SRT) is used to simulate steam-water DCC phenomenon. The simulation results are compared with the experimental data and show reasonable agreement. The effects of rolling motion on DCC for steam injection into a horizontal pipe filled with cold water are numerically investigated. The results show that the additional inertial forces and the average condensation rate increase with the increase of the rolling angle and frequency. The reverse flow of the seawater induced by rolling motion leads to the accumulation of the steam at the lower part of the pipe, resulting in a large pressure pulse. With the increase of rolling angle and frequency, the pressure pulse induced by DCC increases. © 2023, The Author(s).

关键词： Condensation

来源：评论

学校读者我要写书评

暂无评论

Effects of Inlet Conditions on the Two-Phase Flow Water Hammer Transients in Elastic Tube 23rd

Effects of Inlet Conditions on the Two-Phase Flow Water Hamm...

引用

23rd Pacific Basin Nuclear Conference, PBNC 2022

作者： Zhao, Zixiang Duan, Zhongdi Xue, Hongxiang Yuan, Yuchao Liu, Shiwen State Key Laboratory of Ocean Engineering Shanghai Jiao Tong University Shanghai China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9789819910229

Two-phase flow water hammer events occur in the pipelines of the nuclear power systems and lead to transient and violent pressure shock to tube structures. For the sake of operation safety, the occurrence and severity of the two-phase water hammer should be carefully assessed. This paper presents a parameter analysis of the inlet conditions on the two-phase flow water hammer transients, with considering the elastic effect of the tube walls. A numerical model is established for the vapor-liquid two-phase flow based on the two-fluid six-equation modelling approach, with incorporating correlations and criterions for two-phase flow regime, interfacial interactions and heat transfer. The governing equations are transformed to matrix form expressed by characteristic variables, and solved using the splitting operator method and the total variation diminishing scheme. The accuracy of the model is verified against the experimental data in open literature. Then, the model is applied to investigate the effect of inlet velocity and inlet water temperature on the two-phase flow water hammer transients. The simulation results show that the increase of inlet velocity increases the pressure peak values and brings forward the onset of water hammer, and the increase of inlet temperature decreases the pressure shock. A comparison of the water hammer results between the elastic tube and rigid tube is further presented, and the effect of the elastic modulus on the water hammer is analyzed. The results also show that the pressure peak is largely affected by the tube diameter. © 2023, The Author(s).

关键词： Condensation

来源：评论

学校读者我要写书评

暂无评论

MATLAB/Simulink-Based Simulation Study of Small Pressurized Water reactor Nuclear Steam Supply system

MATLAB/Simulink-Based Simulation Study of Small Pressurized ...

引用

Information Engineering (ACIE), IEEE Asia Conference on

作者： Jie Chen Kai Xiao Mengwei Mengwei Zhao Zhao Ke Huang Pengcheng Yang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

Accurate and reliable modeling and simulation is the key prerequisite for intelligent control technology research of nuclear power plant. For the nuclear steam supply system (NSSS) of small pressurized water reactor under bi-stable steady state operation scheme, this paper firstly establishes the models of the core, regulator, steam generator and other components. Then, the nuclear steam supply system platform (NSSSP) of small pressurized water reactor is built based on Matlab/Simulink. Simulations are carried out to analyze the normal operation transient and load rejection transient in the water supply flow control mode. The accuracy and reliability of NSSSP are verified to beconsistent with the commercial program RETRAN.

关键词：

来源：评论

学校读者我要写书评

暂无评论

Research and Verification of the One-Step Resonance and Transport Methods Based on the Openmoc Code

SSRN

引用

SSRN 2024年

作者： Zhao, Chen Wang, Lianjie Chen, Zhang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

With the continuous improvement of computer hardware capabilities, the one-step method in reactor physics has become one of the important research directions in recent two decades. OpenMOC is an open-source MOC code developed by MIT, with C++/Python hybrid programming and three-dimensional transport calculation capabilities. Based on the OpenMOC code, the following work was carried out. Firstly, the global-local resonance method with multi-group and continuous neutron libraries was researched and established. Next, based on the 2D and 3D MOC solver, the 2D/1D and the MOC/DD transport methods were realized in OpenMOC. Finally, verification of the transport and resonance methods was conducted using the C5G7 macro benchmark and the VERA micro benchmark. The numerical results demonstrated that the average eigenvalue deviation was 44pcm and average maximum pin power distribution deviation was 0.37% in the VERA-2 benchmark, which showed the good accuracy of the resonance method. As for the transport method, 3DMOC method exhibited better accuracy in strong anisotropic cases, but the computational time was 38 times that of the 2D/1D method. © 2024, The Authors. All rights reserved.

关键词： Computer hardware

来源：评论

学校读者我要写书评

暂无评论

Research on Hybrid Modeling Method Based on Mechanism Model and BP Neural Network

Research on Hybrid Modeling Method Based on Mechanism Model ...

引用

Information Engineering (ACIE), IEEE Asia Conference on

作者： Jie Chen Yanqiu Zheng Qing Chu Guanfu Jiang Jing Li Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

reactor system modeling is the premise of reactor control system design. The common commercial thermal and hydraulic analysis programs like RELAP5, RETRAN have complex structure and slow operational speed, which are not conductive to the transplantation and improvement of reactor system. In order to realize the rapid development of reactor control system, this paper carries out the mechanism modeling of the reactor system in Matlab/Simulink, and then introduce BP neural network to establish the hybrid model, which improves the modeling accuracy to support the design of reactor system. For small pressurized water reactor, we firstly take analytical modeling method to build the core mechanism model and its state space model through three conservation principles and the operating mechanism of core. Based on analyses, we can conclude that the parameter error and structural error of the mechanism model is caused by the assumption and simplification during modeling, and choose the parameter with the most influence (the feedback coefficient of the coolant temperature) as the corrected parameter in the BP neural-based hybrid modeling process. After that, according to the dual constant operation scheme of small pressurized water reactors, and the gradient descent method of BP network, the hybrid model of core is built and the parameter error and structure error of the mechanism modeling are corrected online. The simulation results show that the proposed hybrid modeling method can accurately simulate the reactor operate state. Thus, the proposed hybrid model is accurate and effective.

关键词：

来源：评论

学校读者我要写书评

暂无评论

Reliability Analysis of Nuclear Safety-Class DCS ESFAS Based on FTA 7th

Reliability Analysis of Nuclear Safety-Class DCS ESFAS Based...

引用

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

作者： Zhang, Xu Peng, Hao Feng, Shi-Man Yang, Jing-Hua Chen, Shi-Yong Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China PowerChina Sichuan Electric Power Engineering Co. Ltd Chengdu610041 China

ISBN: (纸本)9789819934546

Nuclear safety-class DCS realizes reactor safety protection function, which is directly related to the safe and stable operation of nuclear power plants, so its reliability should be analyzed and optimized. In this paper, the engineered safety features actuation system in nuclear safety-class DCS is analyzed through the control instruction logic flow involved in the structure, according to the components of the series and parallel or voting logic and other logical relations to bulid a fault tree model. Using fault tree model, the reliability degradation trend is obtained, and the minimum cut set, importance degree and other parameters are quantitatively calculated. According to overhaul cycle of nuclear power plant, a maintenance optimization method for engineered safety features actuation system is proposed, and some optimization suggestions are given. © 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

NUMERICAL INVESTIGATION ON DIRECT CONTACT CONDENSATION CHARACTERISTICS OF STEAM INJECTION INTO COLD-WATER PIPE UNDER HEAVING CONDITION 30

NUMERICAL INVESTIGATION ON DIRECT CONTACT CONDENSATION CHARA...

引用

30th International Conference on Nuclear Engineering, ICONE 2023

作者： Wang, Zhiwei He, Yanping Duan, Zhongdi Huang, Chao Liu, Shiwen State Key Laboratory of Ocean Engineering Shanghai Jiao Tong University Shanghai200240 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9784888982566

Direct contact condensation (DCC) is widely appeared in the nuclear power plants and will lead to serious temperature and pressure fluctuations. For ocean nuclear power plants, the DCC is inevitably affected by the sea conditions, such as rolling, heaving motion. In this study, the integration of volume of fluid model (VOF) and condensation model is adopted to simulate the DCC characteristics under heave conditions. The interfacial heat and mass transfer are calculated by user-defined functions (UDF). The additional inertial force method is used to describe the heave motion. First, the DCC numerical model under heave motion is validated by the experimental data, which coincides well with the experiment results. Then, the characteristics of DCC under different heave parameters are numerically studied. The results show that the average condensation rate increases with an increase in heave amplitude, decreases with an increase in heave period. This is mainly because the heave motion will cause the liquid phase to impact the upper pipe wall, and increasing the contact area of vapor and subcooled water. The pressure oscillations induced by DCC are more complicated under heaving conditions. With heave period continuing to change, the formation mechanisms of the pressure peak are different. When the heave period is relatively small, the pressure peak is mainly induced by the acceleration of water phase under high frequency heaving motion. With an increase in the heave period, the heaving motion accelerated the formation of isolated steam bubble, and caused the condensation induced water hammer (CIWH) events, which in turn induced the pressure peak. In addition, the pressure peak is proportional to the heave amplitude. In summary, the direct contact condensation characteristics are more sensitive to the heave period under heaving conditions. These qualitative conclusions may serve as a reference for direct contact condensation simulations under heaving conditions. © 2023 by

关键词： Nuclear power plants

来源：评论

学校读者我要写书评

暂无评论

Modelling Analysis of Non-uniform Flow and Heat Transfer in Parallel Rectangular Channels During Flow Blockage Condition 23rd

Modelling Analysis of Non-uniform Flow and Heat Transfer in ...

引用

23rd Pacific Basin Nuclear Conference, PBNC 2022

作者： Chen, Jiayue Chen, Huandong Wang, Xiaoyu Wang, Zefeng Sino-French Institute of Nuclear Engineering and Technology Sun Yat-Sen University Zhuhai610213 China Science and Technology On Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9789811987793

In order to establish the non-uniform flow and heat transfer modelling method in parallel rectangular channels, as an additional technique and tool for safety analysis of plate-type fuel, one dimensional two-fluid model coupled with two-dimensional heat conduction of fuel are used to develop a special code for non-uniform flow and heat transfer simulation during flow blockage condition. The flow distribution and fuel temperature field are obtained under different blockage conditions. The two-dimensional heat conduction model are testes under four different power distributions. The simulation results show that mass flow and heat transfer between parallel channels would redistribute after blockage. And the two-dimensional heat conduction model predicted more uniform temperature profile of fuel plate cross-section. Thus, the modelling method used in this paper can be used in the parallel rectangular channels prediction in non-uniformly flow and heat transfer phenomenon. © 2023, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Two phase flow

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：