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Verification Method and Basic Guarantee of RPS Availability in Nuclear Power Plant 5th

Verification Method and Basic Guarantee of RPS Availability ...

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

作者： He, Xian-Jian Liu, Ming-Ming Zhang, Qing Luo, Xiao-Jun Wen, Jing Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9789811634550

The third generation nuclear power reactor protection system (RPS) based on computer technology, that is, safety DCS system, is designed with large-scale integrated circuits and real-time embedded software, which has the characteristics of complex structure, large system scale and high verification difficulty. In order to ensure the safe operation and economic benefits of nuclear power plants, RPS needs not only reliability and stability, but also high availability. In order to explore the feasibility of verification of DCS availability index, based on Hualong One safety DCS engineering prototype, a set of availability testing methods and basic guarantee conditions suitable for DCS suppliers are summarized for discussion and exchange. © 2021, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Nuclear power plants

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An Ergonomic Analysis of Main Control Room Console in Nuclear Power Plant Based on Jack 5th

An Ergonomic Analysis of Main Control Room Console in Nuclea...

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

作者： Li, Yu-Tong Liu, Ming-Ming Huang, Qing-Huai Gao, Nan Liu, Guan-Ron Zhou, Mao Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9789811634550

In the process of human factor design and preliminary verification of the control room console in Nuclear Power Plant, traditional 2D human model design and analysis method is commonly used. However the results turn to be inaccurate and time-consuming. With the help of human simulation tool Jack, quick and precise analysis can be achieved. This paper puts forward the human factor engineering analysis of main control room console in nuclear power plant based on Jack including the visibility, accessibility, and collision detection. By comparing this method with traditional 2D design, conclusion can be drawn that Ergonomic Analysis of main control room console Based on Jack is more comprehensive and accurate, thus largely increasing the design efficiency and quality. © 2021, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Nuclear power plants

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CFD ANALYSIS ON THE SMALL MODULE reactor (ACP100) PRS RETURN LINE THERMAL STRATIFICATION PHENOMENON 29

CFD ANALYSIS ON THE SMALL MODULE REACTOR (ACP100) PRS RETURN...

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2022 29th International Conference on Nuclear Engineering, ICONE 2022

作者： Peiying, Li Cai, Zhiyun Zhang, Yulong Liu, Hang Liu, Minghao Ye, Zhu Tao, Shuchang Liu, Xianghong Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China

ISBN: (纸本)9780791886434

The return line of the passive residual system(PRS) of ACP100 is connected to the direct injection nozzle of the pressure vessel. It is a non-isolated dead pipe containing coolant, and there is no insulation layer. The temperature difference between the two sides of the pipe is large, which is prone to thermal stratification. This paper uses FloEFD software to carry out CFD simulation analysis and research on the thermal stratification phenomenon of the pipeline in normal operation and accident conditions. The scope of the return line analysis in this paper begins with the isolation valve at the outlet and ends with the direct injection nozzle on the pressure vessel. The finite volume method is used to solve the model, and the standard k-Ε two-equation model is used for turbulence simulation. The pipeline system adopts a mesh refinement strategy according to the flow channel and wall thickness in the pipeline to obtain a reasonable mesh distribution. The results show that during normal operation, there is obvious thermal stratification at the exit of the PRS isolation valves, and there is a certain vortex in the tube, which can promote the heat exchange between the reactor pressure vessel and the PRS return pipeline;When PRS put into operation, a large temperature gradient is generated at the interface of the annular cavity of the pressure vessel, and the influence of thermal stress and cyclic thermal shock needs to be considered, and an obvious vortex will be formed nearby to promote the rapid heat exchange of cold and hot water in the nearby area. The result of this paper can provide input for PRS return line thermal stress and thermal cycling impact analysis. Copyright © 2022 by ASME and a non-US government agency.

关键词： Vortex flow

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Research on Performance Optimization of Nuclear Power system Based on Improved Genetic Algorithm

Research on Performance Optimization of Nuclear Power System...

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作者： Yang, Bo Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institution of China Sichuan Chengdu China

According to the typical design of the secondary loop system of marine nuclear power plant, the physical model of the main components of the secondary circuit steam turbine, condenser, feed water pump and preheater is established by using the MATLAB software. The main performance parameters of the second loop are analyzed, and the efficiency calculation of simple Rankine cycle and Rankine cycle with exhaust gas is completed. The optimization direction of system parameters can be obtained by performance analysis. © 2021, The Author(s), under exclusive license to Springer Nature Switzerland AG.

关键词： Rankine cycle

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A simplified two-node coarse-mesh finite difference method for pin-wise calculation with SP3

A simplified two-node coarse-mesh finite difference method f...

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2020 International Conference on Physics of reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020

作者： Zhao, Wenbo Yu, Yingrui Chai, Xiaoming Ning, Zhonghao Zhang, Bin Cai, Yun Liu, Kun Peng, Xingjie Yu, Junchong Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China

ISBN: (纸本)9781713827245

For accurate and efficient pin-by-pin core calculation of SP3 equations, a simplified two-node Coarse Mesh Finite Difference (CMFD) method with the nonlinear iterative strategy is proposed. In this study, the two-node method is only used for discretization of Laplace operator of the 0th moment in the first equation, while the fine mesh finite difference (FMFD) is used for the 2nd moment flux and the second equation. In the two-node problem, transverse flux is expanded to second-order Legendre polynomials. In addition, the associated transverse leakage is approximated with flat distribution. Then the current coupling coefficients are updated in nonlinear iterations. The generalized eigenvalue problem from CMFD is solved using Jacobi-Davidson method. A protype code CORCA-PIN is developed. FMFD scheme is implemented in CORCA-PIN as well. The 2D KAIST 3A benchmark problem and extended 3D problem, which are cell homogenized problems with strong absorber, are tested. Numerical results show that the solution of the simplified two-node method with 1×1 mesh per cell has comparable accuracy of FMFD with 4×4 meshes per cell, but cost less time. The method is suitable for whole core pin-wise calculation. © The Authors, published by EDP sciences. This is an open access article distributed under the terms of the Creative Commons Attribution License 4.0 (http://***/licenses/by/4.0/).

关键词： Nonlinear equations

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design of High Uniformity and High Energy Efficiency Illumination Lens Based on Hypothetical Point Source Ensemble

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Guangxue Xuebao/Acta Optica Sinica 2025年第7期45卷

作者： Li, Ziheng Huo, Furong Xue, Changxi Yang, Chao Dong, Bo School of Optoelectronic Engineering Changchun University of Science and Technology Jilin Changchun130022 China Key Laboratory of Advanced Optical System Design and Manufacturing Technology of Universities of Jilin Province Changchun University of Science and Technology Jilin Changchun130022 China

Objective With the rapid advancement of modern science and technology, illumination systems have become an indispensable part of daily life. In fields such as road, medical, and industrial applications, a well-designed illumination system can significantly enhance safety. Therefore, designing an illumination system with a distributed light pattern that meets human needs has become a key focus in the lighting industry. Light emitting diodes (LEDs), with their advantages of environmental friendliness, energy efficiency, and high performance, have gradually replaced traditional light sources and are now the dominant light solution in the market. However, LEDs often require secondary optical design to achieve more uniform and efficient illumination, meeting the specific lighting needs of different environments and improving overall lighting quality and experience. In this paper, we propose a new method for designing a uniform lighting lens in the context of illumination engineering. Methods In light of the luminous characteristics of LED light sources, a novel hypothesis is proposed for designing extended LED light sources, treating the extended light source as a collection of infinite point sources. The divergence halfangle limit for each small point source is strictly defined, and a uniform internal freeform surface is designed to serve as a secondary light source. The external freeform surface then maps the uniform secondary source to the target surface, a method called the hypothetical point source ensemble (HPE). Based on the inner freeform surface, the outer surface is designed by analyzing the point-to-point energy mapping from the light source to the illuminated plane using the source-target mapping method. We derive the corresponding theoretical model and a new formula for calculating the emitted light angle. The point convergence of the outer freeform surface is calculated using Snell’s law in vector form and the tangent iteration method. The discrete point cl

关键词： Optical design

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Structural design and Dynamic Analysis of Nuclear Safety DCS Cabinet with Light-Weight and Impact Resistance 5th

Structural Design and Dynamic Analysis of Nuclear Safety DCS...

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

作者： Dai, Jun-An Liu, Ming-Xing Wu, Xiao Chen, Zhi Wang, Dong-Wei Li, Fa-Qiang Yao, Chang-Wen Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9789811634550

Safety digital control system (DCS) cabinet, as a carrier for the electronic devices, plays a significant role in ensuring the normal operation of the nuclear power plant. In this work, a design idea of impact resistant cabinet frame with high strength and low quality has been proposed. It adopts the design ideas such as flat frame section design, distributed multi-column layout, integrated structural and functional design and preservation of a certain safety margin, which can be used to guide the design of cabinet with high stiffness and strength, small column size and low weight. In addition, finite element analysis and impact response analysis of the designed cabinet are carried out by using ABAQUS-DDAM method. Results show that the designed cabinet is characterized by high stiffness, high strength and low weight, and the cabinet possesses good ability in resisting high level of impact. The design ideas proposed in this research can provide reference for the design of structural parts of other anti-shock electronic equipment. © 2021, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Finite element method

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Study on Uniaxial Tension and Cyclic Deformation Behavior of TA16 at Room Temperature and High Temperature

Study on Uniaxial Tension and Cyclic Deformation Behavior of...

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作者： Shao, Xuejiao Juan, Du kuang, Linyuan Lu, Yuechuan Lu, Jiang Yu, Mingda Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

TA16 is a new type of titanium alloy material, which is widely used in pipeline systems of aerospace, ship and nuclear reactor with high temperature and high pressure. In this paper, the basic mechanical properties and cyclic deformation characteristics of TA16 were obtained by uniaxial tensile test and cyclic loading test at room temperature and high temperature. The Chaboche constitutive model can reasonably describe the cyclic plastic cumulative effect of materials and is provided in ANSYS which is a commercial finite element analysis software. The constitutive model of Chaboche presents a very important evolution criterion of follow-up hardening for ratchet simulation. Based on steady cyclic stress-strain curves which is got by strain control at different temperatures, the material parameters of Chaboche model are obtained by least multiplication fitting for TA16 at room and high temperatures. The constitutive model can used in elastic and elastic finite element analysis of TA16 materials. The experiment results show that TA16 exhibits slight cyclic softening under symmetrical strain cycles, and obvious ratcheting behavior under asymmetric stress cycles. When ratcheting strain of the structure reaches a certain saturation state, plastic accumulation will lead to accidental damage of the structure and lead to serious consequences. The stable cyclic stress-strain curves of TA16 at room temperature and high temperature are simulated by Chaboche model. The simulation results are in good agreement with the experimental results, which provides the basic data for the finite element simulation of cyclic deformation behavior of TA16 titanium alloy structure. © Springer Nature Switzerland AG 2020.

关键词： Constitutive models

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Preliminary study on few group cross section representation method based on model tree algorithm

Preliminary study on few group cross section representation ...

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2018 International Conference on Physics of reactors: reactor Physics Paving the Way Towards More Efficient systems, PHYSOR 2018

作者： Zhao, Wenbo Ju, Haitao Yu, Yingrui Chai, Xiaoming Yu, Junchong Peng, Xingjie Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China

ISBN: (纸本)9781713808510

The tabular representation of few-group cross section is widely used for node wise two-step core simulations. However, it may take too much memory usage for pin-by-pin two-step simulations. A few-group cross section representation method for PWR has been developed to reduce memory usage in this paper. The few-group cross sections are represented as the sum of a base term and a collection of partial terms. Each of these terms is fitted by modified model tree. The case matrix of training data set is similar with that of the conventional methods such as the piece wise interpolation and the tabular representation. Two modifications have been made for the model tree algorithm: 1) burnup is the only variable to split data set, 2) linear regression method on nodes of the tree is replaced with polynomial fitting method according to priori knowledge of the relationship between cross sections and state variables. Through the modifications accuracy and generalization ability are achieved without the pruning procedure. Then the lattice calculations for test data set could be canceled. Tests on the typical PWR lattice are performed. Numerical results show that for the worst case the memory usage of this method is less than 30% of the tabular representation, when the maximum error of reactivity is less than 500 pcm. The memory usage for other cross sections is less than 10% with high accuracy. Optimization of the target tolerance criteria should be tested for fast group cross sections. Large errors in thermal group absorption and fission production cross sections lead to large errors in Kinf and it needs more study on regression model. The method combined with the tabular representation might be more suitable for the pin-by-pin two-step simulations. © 2018 International Conference on Physics of reactors, PHYSOR 2018: reactor Physics Paving the Way Towards More Efficient systems. All rights reserved.

关键词： Errors

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Structure topology optimization design and shock resistance study on nuclear power safety DCS cast aluminum cabinet

Structure topology optimization design and shock resistance ...

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2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference

作者： Dongwei, Wang Mingxing, Liu Xiao, Wu Hao, Yan Zhiqiang, Wu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9780791883761

Offshore floating nuclear power plant (FNPP) is characterized by its small and mobility, which is not only able to provide safe and efficient electric energy to remote islands, but to the oil and gas platforms. The safety digital control system (DCS) cabinet, as a carrier for the electronic devices, plays a significant role in ensuring the normal operation of the nuclear power plant. To satisfy the requirements of cabinet used in the sea environment, such as well rigidity, shock load resistance, good seal and corrosion resistance, etc, more and more attention is focused on the cast aluminum cabinet. However, the cast aluminum structure may cause larger weight of cabinet, which inevitability affects the mobility of cabinet, and increases the carried load of ship as well. Therefore, seeking for an effective approach to design a light weight cast aluminum cabinet for the offshore FNPP is definitely necessary. In this work, a frame of cast aluminum cabinet with lightweight is obtained successfully via structure topology optimization design, it is found that the weight of the frame can be reduced to 50% after optimization iterations. Subsequently, the natural frequency of the optimized cast aluminum cabinet is calculated by using ABAQUS, it is seen that the first mode frequency of the frame is beyond 30 Hz, which can meet the basic stiffness requirement. Accordingly, dynamic design analysis method (DDAM) is performed to verify the ability of the optimized cast aluminum cabinet in resisting sudden shock load, and the shock response characteristics of the cabinet are determined. Numerical results support that the optimized frame of cabinet possesses good resistance to high level shock. However, for the assembled cast aluminum cabinet, the vertical shock circumstance turns out to be the most critical condition, high stress and deformation regions occurs at the bracket and column. Reinforcements are proposed to make the bracket stiffer in this shock loading condition. Copyri

关键词： Finite element method

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