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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.

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

SSRN

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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

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

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

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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.

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Research and development of helium-xenon Brayton cycle technology:A review

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National science Open 2024年第6期3卷 188-218页

作者： Weixiong Chen Meihui Song Yiran Qian Hongxing Yu Junjie Yan State Key Laboratory of Multiphase Flow in Power Engineering Xi’an Jiaotong UniversityXi’an 710049China Key Laboratory of Nuclear Reactor System Design Technology Nuclear Power Institute of ChinaChengdu 610200China

Helium-xenon Brayton cycle systems have significant potential as the energy conversion system for small-scale reactors in remote land,deep-sea,and space applications due to a range of advantages,including high cycle efficiency,compact system structures,and chemical *** objective of this review is to provide a comprehensive understanding of the helium-xenon Brayton cycle system based on the projects and ***,the basic information and development history are introduced,and a series of typical designs are ***,the system configurations,cycle parameter analysis and optimization are ***,the key components are classified,such as turbine,compressor,and heat ***,the dynamic processes and control strategies are introduced in different ***,the deficiency and prospect of current research are *** review covers the representative helium-xenon Brayton cycle systems,which could provide a reference for promoting the development of energy conversion systems.

关键词： helium-xenon Brayton cycle cycle analysis heat exchanger dynamic research

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Prediction of Electromagnetic Shielding Effectiveness of DCS Cabinet Based on Neural Network 7th

Prediction of Electromagnetic Shielding Effectiveness of DCS...

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

作者： Zhang, Xu Yang, You-wei Yang, Jing-hua Li, Jun 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

The shielding effectiveness (SE) of structural components is one of the important indicators of electromagnetic compatibility (EMC) performance, and it is related to the size, material, frequency and test points position in the structure. The measurement of SE is governed by a variety of factors. SE of structural components is affected by the measuring antenna size which is adopted to different frequencies and the testability of certain observation points. To address this issue, this paper introduces an example of the SE of DCS cabinet of nuclear power plant control system, where the neural network algorithm was used to build the relationship between spatial location and SE in the cabinet at specified frequency, so that the SE of unknown points could be predicted by the SE of known points. Besids, the model parameters were optimized by training with a large amount of data, the HPR1000 safety-class DCS cabinet was adopted for the verification, and high prediction accuracy was obtained. © 2023, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Nuclear power plants

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Gas Leakage-based Fault Prediction for a Boron-coated Proportional counter 15

Gas Leakage-based Fault Prediction for a Boron-coated Propor...

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15th IEEE Global Reliability and Prognostics and Health Management Conference, PHM-Beijing 2024

作者： Wang, Miao Wei, Wenbin Wan, Bo Huang, Qichang Sun, Shangqing Lu, Weiwei Wu, Chenlu Hong, Shixin Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China CNNP Guodian Zhangzhou Energy Co. Ltd. China Nuclear Power Engineering Co. Ltd. Zhangzhou China

ISBN: (数字)9798350354010

ISBN: (纸本)9798350354010

Large reaction cross-sections, low operating voltage, extended lifespan, good stability, and suitability for high-temperature and intense gamma radiation settings are among the features of boron-coated proportional counter tubes. Consequently, it has been extensively employed in the nuclear-measuring system outside of the reactor, where the source range detector is a boron-coated proportional counter tube. This paper studies boron-coated proportional counter tubes using a comprehensive approach that combines Monte Carlo simulation with lifespan prediction in health management. The wavelet packet decomposition approach was used to extract feature information from the pulse signals of the boron-coated proportional counter tube. A counter tube defect prediction model was established based on a multi-kernel correlation vector machine, where the impact of different wavelet packets and correlation vector machine kernel functions on the model's prediction performance was examined. The study's findings demonstrated that the particle swarm optimization algorithm-optimized multi-kernel correlation vector machine model exhibited superior prediction accuracy for the counter tubes' future operating conditions. The primary goal is to comprehend how gas loss affects gas pressure and to determine the lifespan of detectors within a detector system. © 2024 IEEE.

关键词： Proportional counters

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Wear Characteristics of the Nuclear Control Rod Drive Mechanism(CRDM)Movable Latch Serviced in High Temperature Water

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Chinese Journal of Mechanical Engineering 2022年第2期35卷 111-120页

作者： Tianda Yu Guozhong Fu Yanqing Yu Liting Zhu Maofu Liu Wei Li Qiang Deng Zhenbing Cai The State Key Laboratory of Power Transmission Equipment&System Security and New Technology Chongqing UniversityChongqing 4000442China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu 610041China Tribology Research Institute Southwest Jiaotong UniversityChengdu 610031China Sichuan Huadu Nuclear Equipment Manufacturing Co. LtdDujiangyan 611830China

The current research of nuclear control rod drive mechanism(CRDM)movable latch only makes a simple measurement of wear *** wear volume and difference in various claw surfaces are ignored and the degradation mechanism of each claw surface is not *** this paper,a detailed degradation analysis was carried out on each claw surface of movable latch combined with wear result and worn *** indicate that the boundary of carbide is preferred for corrosion because carbide presents a nobler Volta potential compared to the metal matrix or boundary *** to the oscillation of drive shaft between the claw surfaces of movable latch,the dominant wear mechanism on the upper surface of claw(USC)and lower surface of claw(LSC)is plastic deformation caused by impact *** impact wear will cause the fragmentation of carbides because of the high hardness and low ductility of *** promotes the broken carbides to fall off from the metal *** generated fine carbides(abrasive particles)cause extra abrasive wear on USC when the movable brings the drive shaft upward or *** a result,USC has a higher wear volume than *** research proposes a method to evaluate the wear on the whole movable latches using a 3D full-size scanner.

关键词： CRDM Movable latch Degradation analysis Wear characteristics Carbide

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A Survey on Distributed Network Localization from a Graph Laplacian Perspective

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Journal of systems science & Complexity 2024年第1期37卷 273-293页

作者： HAN Zhimin LIN Zhiyun FU Minyue Artificial Intelligence Institute School of AutomationHangzhou Dianzi UniversityHangzhou 310018China Shenzhen Key Laboratory of Control Theory and Intelligent Systems School of System Design and Intelligent ManufacturingSouthern University of Science and TechnologyShenzhen 518055China Peng Cheng Laboratory Shenzhen 518000China

Network localization serves as a fundamental component for enabling various position based operations in multi-agent systems,facilitating tasks like target searching and formation control by providing accurate position information for all nodes in the *** localization focuses on the challenge of determining the positions of nodes within a network,relying on the known positions of anchor nodes and internode relative *** the past few decades,distributed network localization has garnered significant attention from *** paper aims to provide a review of main results and advancements in the field of distributed network localization,with a particular focus on the perspective of graph *** to its favorable characteristics,graph Laplacian unifies various network localization,even when dealing with diverse types of internode relative measurements,into a unified protocol framework,which can be constructed by a linear method and ensure the global convergence.

关键词： Distributed network localization graph Laplaian sensor network

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A novel approach for radionuclide diffusion in the enclosed environment of a marine nuclear reactor during a severe accident

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Nuclear science and Techniques 2022年第2期33卷 53-65页

作者： Fang Zhao Shu-Liang Zou Shou-Long Xu Xuan Wang Jun-Long Wang De-Wen Tang School of Resource Environment and Safety Engineering University of South ChinaHengyang 421001China Hunan Provincial Key Laboratory of Emergency Safety Technology and Equipment for Nuclear Facilities Hengyang 421001China Shanghai Nuclear Engineering Research and Design Institute Co.LTD Shanghai 200000China Science and Technology On Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu 610213China

A severe accident in a marine nuclear reactor leads to radionuclide leakage,which causes hidden dangers to workers and has adverse effects of environmental *** is necessary to propose a novel approach to radionuclide diffusion in a confined environment after a severe accident in a marine nuclear ***,this study proposes a new method for the severe accident analysis program MELCOR coupled with computational fluid dynamics scSTREAM to study radioactive diffusion in severe *** radionuclide release fraction and temperature calculated by MELCOR were combined with the scSTREAM calculations to study the radionuclide diffusion behavior and the phenomenon of radionuclide diffusion in different space environments of the reactor under the conditions of varying wind velocities of the ventilation system and diffusion *** results show that the wind velocity of the ventilation system is very small or zero,and the turbulent diffusion of radionuclides is not obvious and diffuses slowly in the form of condensation sedimentation and gravity *** the wind speed of the ventilation system increases,the flow of radionuclides meets the wall and forms eddy currents,affecting the time variation of radionuclides diffusing into chamber *** wind velocity of the ventilation system and the diffusion speed has opposite effects on the time variation trend of radionuclide diffusion into the four chambers.

关键词： Radionuclide diffusion MELCOR coupled with scSTREAM Severe accident Marine nuclear reactor

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

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

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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

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