检索结果-内蒙古大学图书馆

2022 29th International Conference on Nuclear Engineering, ICONE 2022

作者： Zhu, Ye Xiang, Cheng Wei, Liu Zhiyun, Cai Yun, Ren Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9780791886410

The steam generator tube rupture (SGTR) of a nuclear power plant is a transient that is subject to numerous studies. The casing once-through steam generator has great heat-transfer capacity due to its dual-layer heat transfer structure. Base on the structure and operational characteristic of casing once-through steam generator used in small module reactor (SMR), a graphical model is designed using process module in APROS. Operating parameters of the casing once-through steam generator is simulated under steady state of different power load and SGTR condition. According to the results, the enthalpy and the temperature of secondary side outlet first increases and then decreases with the increasing power load and reaches the greatest value when the power load is 60%. Further study the impact of the position and degree of the breakage on the operating characteristics of the casing once-through steam generator when the steam generator tube rupture. The results show that the influence on the operation characteristic of the casing once-through steam generator increase when the tube rupture takes place in the position which is near the primary side inlet. And when the size of tube rupture becomes larger, the leakage mass flow from primary side to secondary side increase, thus cause the enthalpy and the temperature of secondary outlet further decrease. The simulating results fit theoretical analysis, showing that the casing once-through steam generator can be simulated accurately in APROS. Reference and guidance can be provided for the design and optimization of casing once-through steam generator as well as the safety analysis. 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 and verification of SNTA code system for SCWR core steady state analysis 23

Development and verification of SNTA code system for SCWR co...

引用

23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015

作者： Wang, Lianjie Zhao, Wenbo Yang, Ping Ma, Yongqiang Lu, Di Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9784888982566

A coupled neutronics/thermal-hydraulics three dimensional code system SNTA is developed for SCWR core steady state analysis by modular coupling the improved neutronics nodal methodological code and SCWR thermal-hydraulic sub-channel code. The problem of CSR1000 core is studied to verify SNTA. The results calculated by SNTA are agreed well with those by CASIR and SRAC. SNTA is more efficient than CASIR and SRAC whose neutronics modules are based on the Finite Difference Method. The numeric results show that SNTA can be well applied to SCWR core steady state analysis and core concept design. Copyright © 2015 by JSME.

关键词： Finite difference method

来源：评论

学校读者我要写书评

暂无评论

Determination of Hardware Logic Drawing Simulation Modeling Criteria and Its Application in Nuclear Safety-Class DCS 6th

Determination of Hardware Logic Drawing Simulation Modeling ...

引用

6th International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant, ISNPP 2021

作者： Zhang, Xu Chen, Shi-Yong Yao, Zhang Deng, Zhi-Guang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9789811911804

In digital control system (DCS) design, independent hardware logic circuit design is usually used to deal with common causes failures of software. Due to the distinct difference between the design criteria of electrical design diagram and logic schematic diagram, the hardware logic verification should be carried out in the form of translation simulation. In this paper, the modeling criteria of DCS hardware logic simulation are summarized. The modeling criteria take into account both the standard engineering hardware logic drawing specifications and the characteristics of Simulink platform, and the DCS hardware logic electrical design information is translated to the Simulink platform for automatic redrawing according to specific criteria. A complete hardware logic simulation system was established based on the modeling criteria, and the application was verified in HPR 1000 Zhangzhou nuclear power plant project. © 2022, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Digital control systems

来源：评论

学校读者我要写书评

暂无评论

A revised method to simulate the dynamic characteristic of vibration isolator of main pump 27

A revised method to simulate the dynamic characteristic of v...

引用

27th International Congress on Sound and Vibration, ICSV 2021

作者： Zhang, Wenzheng Xiong, Furui Liu, Shuai Yuan, Zhihao Jiang, Xiaozhou Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9788378807995

It's important to choose suitable kinetic parameters for vibration isolators to simulate the dynamic characteristic. The kinetic parameters have significant influence on the vibration reduction of vibration isolators. In this paper, the kinetic parameters of two kinds of metal-rubber (MR) vibration isolators of main pump are measured to accurately acquire the dynamic characteristic. The origin impedance and cross point impedance data is tested on the testing platform. The four-terminal parameter method is applied to calculate the stiffness and damping value of the MR vibration isolators. Unfortunately, the method can't simulation the influence of the peak value behind the standing wave frequency, which is caused by the internal resonance of the vibration isolators. A revised rod vibration model is adopted to simulate the internal resonance, because the rod vibration model can express the high order peak. The numerical results are in good agreement with experimental results. The revised method can be used to simulate the dynamic characteristic of vibration isolators. © "Advances in Acoustics, Noise and Vibration - 2021" Proceedings of the 27th International Congress on Sound and Vibration, ICSV 2021. All rights reserved.

关键词： Kinetic parameters

来源：评论

学校读者我要写书评

暂无评论

DATA DRIVEN METHODS FOR BREAK SIZE AND LOCATION ESTIMATION IN LOCA BASED ON DEEP LEARNING 29

DATA DRIVEN METHODS FOR BREAK SIZE AND LOCATION ESTIMATION I...

引用

2022 29th International Conference on Nuclear Engineering, ICONE 2022

作者： Yuan, Peng Deng, Jian Qiu, Zhifang Zhu, Dahuan Huang, Tao Li, Zhongchun Du, Peng Xu, Qinglan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9780791886427

Loss of coolant accident (LOCA) is one of the most important accidents in thermal hydraulic design of nuclear power plant. The traditional analysis method is difficult to realize the rapid prediction of the size and location of the break in the LOCA, while machine learning provides an idea for the rapid diagnosis of the initial cause of LOCA. In this paper HPR1000 which is independently designed by China was taken as the object, the process of LOCA under various break location and sizes is studied by using the advanced reactor system analysis code ARSAC (Advanced reactor system Analysis Code). The key thermal hydraulic parameters including temperature, pressure, flow rate and water level in the transient process of LOCA are analyzed, and a series of data sets are generated. Based on convolution neural network algorithm of deep learning, the transient thermal hydraulic parameters of HPR1000 under different working conditions are learned and the accident diagnosis model is obtained. By comparing with the test data, the trained model can quickly and accurately predict the size and location of LOCA, which can be subsequently extended to the diagnosis of other kinds of accidents in nuclear power plants and has certain application prospects. Copyright © 2022 by ASME.

关键词： Location

来源：评论

学校读者我要写书评

暂无评论

COMPARISON OF NUMERICAL ANALYSIS METHODS OF COOLANT ENVIRONMENTAL FATIGUE BASED ON STRAIN RATE CONTROL 29

COMPARISON OF NUMERICAL ANALYSIS METHODS OF COOLANT ENVIRONM...

引用

2022 29th International Conference on Nuclear Engineering, ICONE 2022

作者： Shao, Xuejiao Xie, Hai Zhang, Yixiong Xiong, Furui Wang, Xinjun Shi, Kaikai Yu, Mingda Huang, Xuan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9780791886397

In this paper, the transformed strain rate of environmental fatigue correction factor (Fen), which is used to consider the influence of PWR primary coolant environment on material fatigue, is studied. EPRI's guideline and theAFCEN's probationary phase rule (RPP) No.3 of Volume VI in RCC-M 2017 edition provide two different calculation methods of transformed strain rate separately. NUREG CR-6909 gives two versions of prediction models of Fen for Low alloy steel, nickel base alloy and austenitic stainless steel which are the three main materials of the primary circuit system. In this paper, the model and transients of Sample 2 in EPRI's guideline are selected for calculation and comparison, so as to verify whether the analysis method is reasonable. Firstly, the fatigue analysis in air is carried out, and then based on the combination, the detailed calculation of strain rate is carried out to calculate environmental fatigue results. The analysis results are compared with the results of guideline, and the valuesare close. Then, the main pipeline safety injection nozzle components with small fatigue margin in PWR are selected to carry out environmental fatigue analysis. In the analysis, different methods of calculating modified strain rates are used, and different prediction models in CR-6909 are *** coefficient of Fenintegratedin RPP3 isconsidered, and the effects of various calculation methods on the results are compared. The results show that for austenitic stainless steel, the results of RCC-M RPP3 method are mostly less than those of EPRI guidelines. Compared with the prediction model of NUREG CR-6909 version 0, the prediction model version 1 greatly decreases the Fen results. Copyright © 2022 by ASME.

关键词： Strain rate

来源：评论

学校读者我要写书评

暂无评论

Acoustic indeced vibration research of dryer in steam generator 26

Acoustic indeced vibration research of dryer in steam genera...

引用

26th International Congress on Sound and Vibration, ICSV 2019

作者： Xianhui, Ye Fengshou, Zhang Fengchun, Cai Wenzheng, Zhang Furui, Xiong Haiyang, Song Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9781999181000

The acoustic induced vibration of dryer (also called secondary separator) in steam generator in nuclear power plants is a concern in recent years. Periodic vibrations of long-term operation can lead to fatigue damage of structural components, posing a safety hazard. In this paper, the finite element analysis model of the dryer structure in steam generator of "Hualong-1" nuclear power plant was established, and the acoustic induced vibration characteristics of the structure were studied. Firstly, the acoustic excitation of the dryer structure was discussed, and the excitation inputs were obtained, including the maximum static pressure and the maximum pressure power spectrum density. Then the finite element model was established by ANSYS and the weak parts of the dryer structure were determined by the vibration characteristics combined with the acoustic excitation characteristics analysis. Finally, the structural strength and fatigue characteristics of the dryer structure under two different inputs of the acoustic load were investigated. The analysis of vibration characteristics shows that the main weak parts of the dryer structure are the vertical partition plate and the perforated plate. The static pressure analysis shows that the stress intensity of the two weak plates is less than the limit. In the study of pressure power spectral density, the maximum dynamic stress intensity and alternating stress of the vertical partition plate and the perforated plate are also less than the limit. The research results indicate that the acoustic induced vibration response of the dryer structure is within the acceptable range © Proceedings of the 26th International Congress on Sound and Vibration, ICSV 2019. All rights reserved.

关键词： Steam generators

来源：评论

学校读者我要写书评

暂无评论

A method for predicting the configuration of corium pool in RPV lower plenum

A method for predicting the configuration of corium pool in ...

引用

2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018

作者： Liu, Lili Yu, Hongxing Chen, Liang Jian, Deng Chunrui, Deng Dan, Zhang Xiaoli, Wu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9780894487552

The configuration of a corium pool in the lower plenum of reactor vessel is very important for validity of maintaining reactor vessel integrity under IVRERVC (In-Vessel corium Retention through External reactor Vessel Cooling) condition. A method is designed to predict the configuration of corium pool for an Advanced China PWR, call ACP1000 after entire melt dropping into the lower plenum. It takes into account both thermo-chemical reaction of oxides and metals in corium and the influence of different paths of corium relocated from core region into the lower plenum. The reasons why a three-layer pool has not been observed in the MASCA and COSMOS tests are given by this method. The method is applied to investigate the corium configuration of ACP1000 after a hypothetical station blackout (SBO) accident. It is shown that the stratification of the corium pool is related to the relocation paths of the corium. In the case of downward relocation, a two-layer melt pool with a metal layer on the top is formed. For the sideward relocation, the configuration shows a stratified pool consisting of a dense metal layer on the bottom, an oxide layer in the middle and a light metal layer on the top. © 2018 American Nuclear Society. All rights reserved.

关键词： Pressurized water reactors

来源：评论

学校读者我要写书评

暂无评论

EVALUATION OF THE PARAMETER IMPORTANCE CHANGES OVER TIME FOR NUCLEAR reactor TRANSIENTS 29

EVALUATION OF THE PARAMETER IMPORTANCE CHANGES OVER TIME FOR...

引用

2022 29th International Conference on Nuclear Engineering, ICONE 2022

作者： Xiong, Qingwen Song, Gongle Du, Peng Huang, Tao Deng, Jian Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9780791886410

The uncertainty analysis and sensitivity analysis are two important parts in the safety analysis of nuclear reactor accidents, and the main purpose of the sensitivity analysis is to quantify the importance of the input on the target output. In typical sensitivity analysis for the nuclear reactor transients, specific techniques such as the regression analysis or correlation coefficient analysis are utilized to calculate the sensitivity measures of the inputs on the target output at scalar points, for instance the peak cladding temperature (PCT). However, the phenomena and parameters vary significantly over time during the transients, thus the influence of each input also changes. In order to evaluate the importance changes of the inputs on the target output over time, a time-dependent global sensitivity analysis technique was developed base on the B-spline function system of the functional data analysis, the landmark registration strategy, and an efficient moment-independent sensitivity analysis method. The developed technique was adopted in the sensitivity analysis of a large break loss of coolant accident (LBLOCA) of the nuclear reactor, and the time-dependent sensitivity measures of the inputs on the maximum cladding temperature were acquired and analyzed. Results showed that the proposed technique is capable of evaluating the importance changes of the key parameters in nuclear reactor accident transients. Copyright © 2022 by ASME.

关键词： Sensitivity analysis

来源：评论

学校读者我要写书评

暂无评论

Stacking, Strain-Engineering Induced Altermagnetism, Multipiezo Effect, and Topological State in Two-Dimensional Materials

arXiv

引用

arXiv 2025年

作者： Xun, Wei Liu, Xin Zhang, Youdong Wu, Yin-Zhong Li, Ping Jiangsu Engineering Research Center for Design and Application of Intelligent Detection Equipment School of Electronic Engineering Jiangsu Vocational College of Electronics and Information Huaian223003 China School of Physical Science and Technology Suzhou University of Science and Technology Suzhou215009 China State Key Laboratory for Mechanical Behavior of Materials Center for Spintronics and Quantum System School of Materials Science and Engineering Xi’an Jiaotong University Shaanxi Xi’an710049 China State Key Laboratory for Surface Physics Department of Physics Fudan University Shanghai200433 China State Key Laboratory of Silicon and Advanced Semiconductor Materials Zhejiang University Hangzhou310027 China

Altermagnetism, as a newly identified form of unconventional antiferromagnetism, enables the removal of spin degeneracy in the absence of net magnetization that provides a platform for the low power consumption and ultra-fast device applications. However, the rare attention has been paid to the relationship between stacking, strain and altermagnet, multipiezo effect and topological state. Here, we propose a mechanism to realize the altermagnet, multipiezo effect, and topological state in two-dimensional materials by the stacking and strain engineering. Based on the analysis of symmetry, we find that the spin splitting feature related to the Ut, PTt, MzUt, or MzPTt symmetries in altermagnet multilayers. In addition, we find that the stacking engineering can effectively realize the transform from antiferromagnetism to altermagnetism and semiconductor to metal for the Jauns bilayer V2SeTeO. More interestingly, the strain not only induces an intriguing multipiezo effect, encompassing the piezovalley, piezomagnetism and piezoelectric, but also achieves the abundant topological phase. Our findings offer a generalized direction for manipulating the spin splitting, valley polarization, and topological states, promoting practical application of valleytronic and spintronic devices based on two-dimensional altermagnets. © 2025, CC BY.

关键词： Antiferromagnetism

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：