检索结果-内蒙古大学图书馆

Research of Advanced Control Algorithm in Primary Loop Control system 5th

Research of Advanced Control Algorithm in Primary Loop Contr...

5th International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant, ISNPP 2020

作者： Deng, Zhi-Guang Zhu, Bi-Wei Wu, Qian He, Peng Xiang, Mei-Qiong Xu, Tao Qing, Yue National Key Laboratory of Science and Technology on Reactor System Design Technology Chengdu610213 China

ISBN: (纸本)9789811634550

The primary loop system of nuclear power plant is a large-scale control system with serious coupling between loops and complex objects. In order to solve the problem of integrated control of primary loop core power, stabilizer pressure and water level, and steam generator water level, this paper applies improved predictive control algorithms to each sub-control system on the basis of mechanism modeling. For the strong non-linear problem of water level control, a multi-model predictive controller is constructed through linearization at each typical operating point. The simulation results show that the application of advanced predictive control algorithm to the primary loop control system has achieved good control performance, and it also lays a solid foundation for subsequent practical engineering applications. © 2021, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Water levels

来源：评论

学校读者我要写书评

暂无评论

Assessment of Coupled Effect of Steam Pipes on Seismic Analysis of reactor Coolant system 7

Assessment of Coupled Effect of Steam Pipes on Seismic Analy...

引用

7th International Conference on Environmental science and Civil Engineering, ESCE 2021

作者： Li, Lijuan Liu, Zhenyu Li, Hui Ye, Xianhui Ai, Honglei National Key Laboratory of Science and Technology on Reactor System Design Technology Chengdu Sichuan China

reactor coolant system is connected with auxiliary pipes, surge pipes and steam pipes. In order to facilitate the dynamic analysis of reactor coolant system, it is necessary to decouple the pipes connected with the reactor coolant system. Although some international standards stipulating requirements for the decoupling of subsystems from the main system, in order to further explore the influence of decoupling steam pipes, the seismic response of reactor coolant system with or without steam pipes is simulated by using ANSYS program. Firstly, the modal analysis of reactor coolant system is carried out to analysis the influence of steam pipes on the resonant frequency of reactor system. Then, the standardized seismic dynamic analysis of reactor system with or without steam pipes is carried out. The nozzle load (inlet and outlet nozzle load of main device, such as reactor pressure vessel, steam generator, pump) and support load (of main device such as reactor pressure vessel, steam generator, pump) are output and compared. According to nozzle load and support load, it can be seen that the steam pipes have little influence on the seismic analysis of reactor coolant system, i.e. steam pipes can be decoupled in the seismic analysis of reactor coolant system. © Published under licence by IOP Publishing Ltd.

关键词： Steam generators

来源：评论

学校读者我要写书评

暂无评论

Experimental Research about Corrosion Effect on Boiling Heat Transfer Performance of Plate-type Samples with Micro-structures 20

Experimental Research about Corrosion Effect on Boiling Heat...

引用

20th International Topical Meeting on Nuclear reactor Thermal Hydraulics, NURETH 2023

作者： Xu, Wei Liu, Xiaojing Ouyang, Kun He, Xiaoqiang College of Smart Engineering Shanghai Jiao Tong University Shanghai200240 China School of Nuclear Science and Engineering Shanghai Jiao Tong University Shanghai200240 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9780894487934

Enormous studies have demonstrated that suitable modification methods, such as micro-structures machining, are adopted to enhance boiling heat transfer performance, especially critical heat flux (CHF) value. This significant improvement can lead to broader application prospect of micro-structured surface in the nuclear power plant scenario. However, little attention has been paid to research the durability of micro-structured surface, and whether strengthening effect can be maintained after a long time of harsh corrosive environment within reactor. In this paper, experimental studies are conducted to research the corrosion effect on boiling heat transfer capability of heating plates with micro-structures. To be specific, microgrooves, pores and columns are machined on metal plate-type samples by laser processing. These samples are placed in autoclave of high temperature and high pressure to simulate the actual conditions, with the corrosion span up to 300 days. After then, saturated pool boiling tests are carried out and high-speed camera is also utilized to quantitatively illustrate the boiling heat transfer characteristics. The experimental results show that the CHF values of different micro-structured samples increase initially and then decreases with increasing corrosion time. In addition, the samples with micro-pores have the largest bubble departure frequency at the beginning of nucleate boiling and those with micro-grooves have the highest CHF value instead. © 2023 Proceedings of the 20th International Topical Meeting on Nuclear reactor Thermal Hydraulics, NURETH 2023. All rights reserved.

关键词： High speed cameras

来源：评论

学校读者我要写书评

暂无评论

DPN: Decoupling Partition and Navigation for Neural Solvers of Min-max Vehicle Routing Problems 41

DPN: Decoupling Partition and Navigation for Neural Solvers ...

引用

41st International Conference on Machine Learning, ICML 2024

作者： Zheng, Zhi Yao, Shunyu Wang, Zhenkun Tong, Xialiang Yuan, Mingxuan Tang, Ke Department of Computer Science and Engineering Southern University of Science and Technology Shenzhen China Department of Computer Science City University of Hong Kong Hong Kong School of System Design and Intelligent Manufacturing Southern University of Science and Technology Shenzhen China China Huawei Noah's Ark Lab Shenzhen China

The min-max vehicle routing problem (min-max VRP) traverses all given customers by assigning several routes and aims to minimize the length of the longest ***, reinforcement learning (RL)-based sequential planning methods have exhibited advantages in solving efficiency and ***, these methods fail to exploit the problem-specific properties in learning representations, resulting in less effective features for decoding optimal *** paper considers the sequential planning process of min-max VRPs as two coupled optimization tasks: customer partition for different routes and customer navigation in each route (i.e., partition and navigation).To effectively process min-max VRP instances, we present a novel attention-based Partition-and-Navigation encoder (P&N Encoder) that learns distinct embeddings for partition and ***, we utilize an inherent symmetry in decoding routes and develop an effective agent-permutation-symmetric (APS) loss *** results demonstrate that the proposed Decoupling-Partition-Navigation (DPN) method significantly surpasses existing learning-based methods in both single-depot and multi-depot minmax *** code is available at. Copyright 2024 by the author(s)

关键词： Sales

来源：评论

学校读者我要写书评

暂无评论

A Transient Model of Sodium Heat Pipe With Phase Change Temperature Difference 29

A Transient Model of Sodium Heat Pipe With Phase Change Temp...

引用

2022 29th International Conference on Nuclear Engineering, ICONE 2022

作者： Ruicheng, Zhong Yugao, Ma Qingzhu, Zhao Jang, Deng Yu, Liu Ding, Shuhua Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China College of Letters & Science University of California Santa BarbaraCA93106 United States

ISBN: (纸本)9780791886502

The heat pipe is the essential component in the heat pipe cooled reactor, it conducts heat through the phase change of the working medium and the circulating flow of gas and liquid. One end of the heat pipe is inserted into the reactor as the evaporation section, while the other end serves as the condensation section connecting to the thermoelectric conversion system. Its heat transfer capacity and temperature distribution under a steady state affect the safety, core temperature and energy conversion efficiency of the heat pipe cooled reactor system. Predicting the heat transfer process and steady-state temperature distribution of the heat pipe is helpful to learn about the heat transfer mechanism inside the heat pipe and key factors affecting its performance. It is also helpful to predict the operating characteristics of the heat pipe cooled reactor system and improve the performance of the heat pipe. The heat pipe is generally considered to be a heat transfer element with good isothermal properties. Past studies, however, proved the significant quantity of its phase-change thermal resistance, resulting in a temperature difference at the gas-liquid interface of the heat pipe that affects the evaporation and condensation. Studies on the relationship between the temperature difference, the working temperature, and heat transfer power of the heat pipe are conductive to building a heat pipe model, to predict the temperature distribution of the heat pipe in a steady state in a much more accurate manner. This paper offered a heat pipe model that applies the temperature difference of the phase change interface to calculate the evaporation and condensation. Meanwhile, a 1-meter-long sodium heat pipe was adopted to carry out steady-state heat transfer experiments. Measured and computed the temperature difference of the phase change interface of the heat pipe under varying power and temperature and conducted the relational equation as the input of the heat pipe model. The mo

关键词： Heat pipes

来源：评论

学校读者我要写书评

暂无评论

The Influence of Turbulators on the Flow and Heat Transfer Characteristic of Helium-Xenon Mixture Inside the Tight Lattice Rod Bundles

SSRN

引用

SSRN 2024年

作者： Wang, Lanxin Shi, Xinhuan Li, Zhongchun Wu, Xiaoli Ding, Shuhua Chen, Wei School of Aeronautics and Astronautics Sichuan University Chengdu610065 China Science and Technology on Reactor System Design Technology Laboratory Chengdu610213 China

The gas-cooled nuclear reactor combined with the closed Brayton cycle is the ideal choice for future high-power space missions, while the helium-xenon mixture is a suitable working medium for the reactor due to its good compressibility and heat transfer capacity. For further development and application of more lightweight compact reactor, the influence mechanism of turbulator structures with different angle and layout on the heat transfer enhancement of helium-xenon mixture in the sub-channel of gas-cooled nuclear reactor is numerically studied. The results show that, due to the vortex and secondary flow induced by the turbulator, the heat transfer is enhanced effectively, and the Nusselt number is fluctuated periodically. Compare the result with different angle, the heat transfer enhancement by the turbulator with 90°angle is relatively small, and the pressure drop is large. Because of the secondary flow in narrow triangular space induced by turbulator with 45°angle, the mixing between the high and low temperature fluids will effective enhanced, the heat transfer enhancement is more significant. The heat transfer performance and thermal efficiency index of different turbulator layout are summarized and compared, which provides the reference for heat transfer design of gas-cooled nuclear reactor. © 2024, The Authors. All rights reserved.

关键词： Helium

来源：评论

学校读者我要写书评

暂无评论

An Interpretable Dynamic Feature Search Methodology for Accelerating Computational Process of Control Rod Descent in Nuclear reactors

SSRN

引用

SSRN 2023年

作者： Huang, Qingyu Xiao, Cong Pang, Zhixin Lin, Yuanfeng Liu, Jia Zhang, Zhuo Zhao, Mengwei Liu, Xiaobo Wang, Yuanmei Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

Within the operational dynamics of a nuclear reactor, the customary approach involves modulating the reactor's power output by means of control rod manipulation, which effectively alters the neutron density across the core. The descent behavior of the control rod drive lines pertains to the intricate motion exhibited by the control rod components within the reactor during its operational lifespan, characterized by conditions of heightened irradiation, temperature, pressure, and complex fluid dynamics. The precise calculation of the control rod descent process is an integral facet of reactor structural design to ensure the safe and reliable operation of the reactor. However, the current computational fluid dynamics-based simulation methods employed for this purpose necessitate extensive grid computations, imposing significant computational burdens in terms of resources and time. In light of this challenge, we present a novel and interpretative algorithm rooted in dynamic similarity feature search. Through comprehensive validation, this algorithm demonstrates remarkable precision with computational results exhibiting an error margin within 10%, while simultaneously achieving a substantial enhancement in computational efficiency of nearly three orders of magnitude when compared to conventional computational fluid dynamics techniques. Notably, this algorithm showcases exceptional versatility, holding immense promise for broad applicability across various operational scenarios encountered during the intricate process of nuclear reactor design. © 2023, The Authors. All rights reserved.

关键词： Control rods

来源：评论

学校读者我要写书评

暂无评论

Cybersecurity Risk Assessment of Nuclear Svdu Based on Attack Tree

SSRN

引用

SSRN 2025年

作者： Wu, Yanqun Wang, Junfeng Ma, Quan Liu, Mingxing Chen, Meiyuan College of Computer Science Sichuan University Chengdu610065 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610000 China

The nuclear power SVDU in nuclear power plants is an important component of the nuclear reactor protection system. With the complete digitalization of the reactor protection system, the risks of cybersecurity attacks have significantly increased. This paper proposes a safety risk assessment method based on an attack tree model to analyze the risk status of the nuclear power SVDU and assess its risk level and security level. Firstly, the typical information security threats faced by nuclear power SVDU are analyzed. Subsequently, an attack tree model of the system is constructed based on the STRIDE model, with four security attributes assigned to the leaf nodes of the tree with reference to the CVSS4.0 system and multi-attribute utility theory. These attributes are quantified through level scoring, and the risk probability of the leaf nodes is calculated using entropy weighting. The risk probability of the root node is then obtained based on the dependency relationship between nodes. Finally, the security risk rating of nuclear power SVDU is obtained. Experimental results demonstrate that the method in this paper more accurately identifies high-risk security threats, predicts possible attack paths, and provides a basis for security protection strategy selection. © 2025, The Authors. All rights reserved.

关键词： reactor shielding

来源：评论

学校读者我要写书评

暂无评论

Highly adaptive triboelectric tactile sensor on the foot of autonomous wall-climbing robots for detecting the adhesion state and avoiding the hazard

引用

Nano Research 2024年第7期17卷 6518-6526页

作者： Zhaoyang Wang Jianhua Liu Ziyu Wang Chang Liu Qingyu Chen Chaofan Zhang Wenbo Zhang Jicang Si Xiu Xiao Peng Xu Minyi Xu Dalian Key Lab of Marine Micro/Nano Energy and Self-powered System Marine Engineering CollegeDalian Maritime UniversityDalian 116026China Information Science and Technology College Dalian Maritime UniversityDalian 116026China Navigation College Dalian Maritime UniversityDalian 116026China Intelligent Biomimetic Design Lab College of EngineeringPeking UniversityBeijing 100871China

Due to the excellent maneuverability and obstacle crossing of legged robots,it is possible for an autonomous legged wallclimbing robots to replace manual inspection of ship exterior ***,when the magnetic adsorption legged wallclimbing robot steps on the convex point or convex line of the wall,or even when the robot missteps,the robot is likely to detach from the ferromagnetic ***,this paper proposes a tactile sensor for the legged magnetic adsorption wall-climbing robot to detect the magnetic adsorption state and improve the safety of the autonomous crawling of the *** tactile sensor mainly comprises a three-dimensional(3D)-printed shell,a tactile slider,and three isometric sensing units,with an optimized *** experiment shows that the triboelectric tactile sensor can monitor the sliding depth of the tactile slider and control the light-emitting device(LED)signal *** addition,in the demonstration experiment of detecting the adsorption state of the robot's foot,the triboelectric tactile sensor has strong adaptability to various ferromagnetic wall ***,this study establishes a robot gait control system to verify the feedback control ability of the triboelectric tactile *** results show that the robot equipped with the triboelectric tactile sensor can recognize the dangerous area on the crawling wall and autonomously avoid the ***,the proposed triboelectric tactile sensor has great potential in realizing the tactile sensing ability of robots and enhancing the safety and intelligent inspection of ultra-large vessels.

关键词： legged wall-climbing robot ship inspection tactile perception triboelectric sensor

来源：评论

学校读者我要写书评

暂无评论

Study on the resource utilization of high fluorine-containing organic waste through fluidized incineration

引用

Waste Disposal and Sustainable Energy 2022年第2期4卷 117-129页

作者： Wenhan Li Zengyi Ma Jianhua Yan Qianming Huang Xingjian Wen Zian Zhai Bochen Huang Shuang Wang Yongqiang Chen Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu610213China State Key Laboratory of Clean Energy Utilization Institute for Thermal Power EngineeringZhejiang UniversityHangzhou310027China Zhejiang Xianchuang Energy&Technology Co.Ltd Jinhua321000China

In this study,the method of fluidized incineration and water washing to recover hydrogen fluoride(HF)was proposed to dispose of high fluorine-containing organic *** resource utilization of the waste was investigated in a fluidized bed incinerator with a disposal capability of 10 t/*** evolution characteristics of fluorine,operation conditions of the incineration system,absorption coefficient for HF by water washing,and HF corrosion during combustion were *** results showed that HF and fluorocarbons were detected as the initial gaseous fluorides released during *** release of HF could be divided into three stages,in which HF was generated from the volatilization of HF in the waste and the hydrolysis of fluorine in water-soluble salts(60–220℃),oxidative decomposition of fluorinated organic components and residual carbon(220–800℃),and hydrolysis of insoluble fluorinated inorganic minerals(800–1000℃).Fluorocarbons could be destroyed through reactions with free radicals H,O,and OH or through single-molecule *** the temperature in the furnace and increasing the content of oxygen and hydrogen in the incineration materials were conducive to reducing the generation of *** sampling and analyzing the bottom slag,bag filter ash and exhaust gas during the field test,the relevant pollutant discharge could meet the national emission *** waste heat utilization of high-temperature flue gas and the recovery of hydrofluoric acid and hydrochloric acid were *** the recovery of HF by water washing,the total absorption coefficients for 1#to 4#packed absorbers were 52.38 kg/(h m^(2)),39.96 kg/(h m^(2)),5.98 kg/(h m^(2))and 3.89 kg/(h m^(2)),*** the actual operation,alumina showed good corrosion resistance to high-temperature HF and could be used as bed materials or refractory ***-temperature corrosion of HF occurred in the quenching heat exchanger,which was damaged after 6 months of continu

关键词： Organic waste Fluorine Fluidized incineration Resource utilization

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：