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SSRN 2024年

作者： Chen, Yiwen Zhang, Dalin Jiang, Dianqiang Li, Wei Wu, Xiaoli Tian, Wenxi Qiu, Suizheng Su, Guanghui Lu, Qi State Key Laboratory of Multiphase Flow in Power Engineering Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology School of Nuclear Science and Technology Xi’an Jiaotong University Xi’an710049 China State Key Laboratory for Strength and Vibration of Mechanical Structures Xi’an Jiaotong University Xi’an710049 China Science Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China China

Helical cruciform fuels are novel in nuclear reactors, potential to increase reactor’s power density. However, the geometry is complicated so influence of it on the fuel performance is not identified yet. In this paper, impact of power density, cross-section parameters, and twist pitch on thermal and mechanical characteristics of fuel used in Fluoride-Salt-cooled high-Temperature Advanced reactor is discussed based on fluid-thermal-mechanical coupling. For thermal features, twist pitch is key while others have few effects. Increase in twist pitch leads to temperature uniformity and rise owing to weaker mixing effects. Fuel center temperature at middle plane of 300mm-pitch rod is 829.58℃, 54.66℃ higher than that of 100mm-pitch rod. Difference of maximum and minimum temperature at 45° cross section of 500mm-pitch rod is 153.62℃, while the figure is only 74.00℃ of 300mm-pitch rod. Besides, axial temperature of cladding outer surface increases wavelike due to complex geometry. For mechanical features, not geometry sizes but temperature affects stress distribution. Maximum Von-Mises stress appears at the elbow, where maximum temperature exists, 116.8MPa under normal conditions, lower than tensile strength of the material. After identifying the influence of these factors, five dimensionless parameters are proposed to evaluate and rate fuel performance based on Technique for Order Preference by Similarity to an Ideal Solution. As a result, an optimization comes up, scoring 0.310, twice more than the original design, owing to the thermal uniformity and mechanical safety. This study provides a reference for identifying and evaluating the performance of helical structure. © 2024, The Authors. All rights reserved.

关键词： Geometry

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Research on Data Optimization technology of Multi-Source Sensing Signal in Nuclear Power Plants

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SSRN 2023年

作者： Liu, Yongchao Li, Tong Xiao, Kai Chen, Jie Tan, Xin Cheng, Jiahao Tan, Sichao Wang, Bo He, Zhengxi Shen, Jihong Gao, Puzhen Tian, Ruifeng College of Nuclear Science and Technology Harbin Engineering University Harbin150001 China Heilongjiang Provincial Key Laboratory of Nuclear Power System & Equipment Harbin Engineering University Harbin150001 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Insitute of China Chengdu610213 China College of Mathematical Sciences Harbin Engineering University Harbin150001 China

The sensor signals collected by the nuclear power plant system equipment are mixed with complex noise information. The uncertainty of sensing data directly affects the application effect of artificial intelligence on nuclear power data mining. Traditional denoising methods have poor adaptability to different noisy data, are highly dependent on researchers, and take a long time. This paper proposes a data optimization technology based on a hybrid adaptive real-time denoising model, which can realize data distribution self-adaptation and algorithm super-parameter self-optimization according to the characteristics of noisy source data. Partition denoising processing of source data. The application of examples and simulation experiments show that this technology can effectively realize the optimization of nuclear power operation data, and provide important technical support for the engineering application of artificial intelligence technology in the complex noise environment of nuclear power plants. © 2023, The Authors. All rights reserved.

关键词： Nuclear energy

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A Method for Hazard Analysis of Floating Nuclear Power Plant Subjected to Ship Collision

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SSRN 2022年

作者： Xiao, Jinxiong Peng, Changhong Zhang, Hang School of Nuclear Science and Technology University of Science and Technology of China No.96 Jinzhai Road Baohe District Hefei230026 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu610213 China

Recently, a technology called floating nuclear power plant (FNPP) has been developed around the world to maximize the use of ocean and nuclear energy. The FNPP is required to investigate the impact of a ship collision during its service period. A rapid and accurate approach for assessing the ship collision hazard is proposed in this work. To begin with, the annual collision frequencies of four different ship types are calculated using the improved collision frequency formula, with standby and supply vessel frequencies of [[EQUATION]] and [[EQUATION]] , respectively, and passing and fishing vessel frequencies of less than [[EQUATION]] . Subsequently, a combination of finite element numerical simulation, back propagation (BP) neural network, and Monte Carlo simulation (MCS) is used to derive the probability density distribution of collision damage measures. Finally, by integrating the annual collision frequency and probability distribution, this paper analyzes the hazard of ship collision with FNPP and derives the hazard curve. © 2022, The Authors. All rights reserved.

关键词： Nuclear power plants

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Safety assessment of UN/Zr fuel with SiC cladding under large break loss-of-coolant accident 14

Safety assessment of UN/Zr fuel with SiC cladding under larg...

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14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water reactor Fuel Performance Conference, TOP FUEL 2019

作者： Qian, Libo Yu, Hongxing Sun, Yufa Deng, Jian Wu, Dan Ding, Shuhua Chen, Wei Li, Zhongchun Chen, Xi Liu, Lili Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan610213 China

Accident Tolerant Fuel (ATF), which is aiming at upgrading safety characteristics of nuclear fuel and cladding under design basis and design extension conditions, has drawn more and more attention since Fukushima accident. By virtue of improved basic properties and oxidation resistance comparing with conventional UO2-Zr, UN(Particle)/Zr(Matrix) fuel pin and SiC cladding (UN/Zr-SiC) is expected to slow down accident progression and to provide wider margin of coping time. In present paper, the improved performance of UN/Zr-SiC fuel system on the Large Break Loss-Of-Coolant-Accident (LB LOCA) is analyzed by Appendix K version of ARSAC code (ARSAC-K). For this reason, the corresponding models in ARSAC-K are modified to achieve the goal: 1) thermal physical properties of SiC;2) equivalent thermal physical properties of UN/Zr composite fuel;3) passive oxidation model of SiC under pure steam condition based on modified Deal-Grove model together with linear volatilization model of SiO2 based on heat/mass transfer analogy. Obtained quantitative results show promising safety enhancement in terms of peak cladding temperature (PCT): the PCT of UN/Zr-SiC fuel is much lower than that of UO2-Zr fuel. Then due to the great safety margin of UN/Zr-SiC fuel under LB LOCA condition, an exploratory investigation of the reduction of safety injection capacity and the increase of reactor nominal power under LB LOCA condition is presented. The results show that from the LB LOCA point of view, UN/Zr-SiC fuel has the potential can to be utilized to reduce safety injection capacity or increase reactor nominal power without reducing the safety margin. Therefore, UN/Zr-SiC fuel is demonstrated to have positive effects on safety and capability of reactor design optimization. Copyright © GLOBAL 2019 - International Nuclear Fuel Cycle Conference and TOP FUEL 2019 - Light Water reactor Fuel Performance *** rights reserved.

关键词： Silicon carbide

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

arXiv

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arXiv 2024年

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 route. Recently, reinforcement learning (RL)-based sequential planning methods have exhibited advantages in solving efficiency and optimality. However, these methods fail to exploit the problem-specific properties in learning representations, resulting in less effective features for decoding optimal routes. This 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 navigation. Furthermore, we utilize an inherent symmetry in decoding routes and develop an effective agent-permutation-symmetric (APS) loss function. Experimental results demonstrate that the proposed Decoupling-Partition-Navigation (DPN) method significantly surpasses existing learning-based methods in both single-depot and multi-depot minmax VRPs. Our code is available at 1 Copyright © 2024, The Authors. All rights reserved.

关键词： Sales

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Simulation analysis on the pressurizer degassing sub-system of module small reactor (ACP100)

Simulation analysis on the pressurizer degassing sub-system ...

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

作者： Zhiyun, Cai Yun, Ren Jianyong, Lai Yulong, Zhang Hang, Liu Xianghong, Liu Minghao, Liu Zhu, Ye Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu610041 China

ISBN: (纸本)9780791883778

A pressurizer degassing sub-system is designed in Module Small reactor(ACP100), which can be used to vent the noncondensable gas dissolved in reactor Coolant during plant shutdown period by opening the remote degassing valve installed on top of the pressurizer. In order to verify the transient characteristic during the whole degassing process, a dedicated transient degassing program is developed based on the improved non-equilibrium multi-region model and the transient degassing model, which is used then to carry out a simulation analysis on this process. Also, the boundary condition models including pressurizer heater power model, pressure spray model, surge line flow model and critical flow model for degassing valve are established. The simulation results show that, under ultimate condition of hot-zero power operation, during the whole degassing process, the Pressurizer's pressure drops to a maximum 0.038MPa, and the water level is raised 0.0637m above the normal level, which means, both of the pressure and water level are within the normal operation band and shall not initiate any safety signal. Meanwhile, the whole transient process lasts about 16 minutes, and then it enters into the stable degassing period. The gas concentration vs time curve is very smooth. It takes about 5.8 hours to remove the gas dissolved in reactor Coolant from 35 ml(STP)/kg to 15 ml(STP)/kg. The analysis shows the Pressurizer Degassing Sub-system is safety, effectively and reliable. Copyright © 2020 ASME

关键词： Plant shutdowns

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Effect of ECAP process on liquid distribution of AZ80M alloy during semi-solid isothermal heat treatment

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Transactions of Nonferrous Metals Society of China 2021年第6期31卷 1599-1611页

作者： Ling-ling FAN Ming-yang ZHOU Yang-yang GUO Yu-wen-xi ZHANG Gao-feng QUAN Key Laboratory of Advanced Technologies of Materials Ministry of EducationSchool of Materials Science and EngineeringSouthwest Jiaotong UniversityChengdu 610031China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu 610213China

Two kinds of semi-solid samples of AZ80−0.2Y−0.15Ca(wt.%)(AZ80M)magnesium alloy were prepared by semi-solid isothermal heat treatment of materials with and without equal channel angular pressing(ECAP)*** microstructures of initial and semi-solid treated samples were compared and *** results showed a significant difference in the liquid phase distribution between three-pass ECAP processed(3P)and as-received samples during the isothermal heating *** semi-solid 3P sample showed a more uniform liquid distribution due to its smaller dihedral ***,the coarsening processes of solid grains of as-received and 3P samples were dominated by the coalescence and Ostwald ripening mechanism,*** difference of coarsening processes was mainly related to the proportion of the high-angle grain boundaries in materials,which further affected the evolution behavior of the liquid pools.

关键词： AZ80M equal channel angular pressing semi-solid microstructure liquid phase distribution coarsening mechanism

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Optimization design for the configuration parameters of helical-coil steam generator volume

Optimization design for the configuration parameters of heli...

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

作者： Fang, Hongyu Wang, Li Zhu, Dahuan Cai, Rong Jiang, Xiaowei Zhang, Dan Qian, Libo Wu, Dan Science and Technology on Reactor System Design Technology Laboratory Chengdu China Sun YAT-SEN University Guangzhou China

ISBN: (纸本)9780791883785

With the development of the nuclear energy industry, small modular reactors (SMRs) have become an important option in China's energy development due to their advantages in terms of safety and economics. The helical-coil steam generator is an important part of SMR, and the structure parameters need to be optimized urgently to reduce costs and improve safety. In this paper, various thermohydraulic parameters were used as indicators for the design quality of the helical-coil steam generator, such as the volume of the equipment, velocity of the flow, maximum temperature of the tubes, and natural circulation capability. The optimization of these target parameters has important theoretical and practical values. The genetic algorithm method is widely used to processes data efficiently, and it is able to reach a optimum design rapidly, which makes it a good choice for the optimization of parameters. The results show that this method could efficiently reduce the volume of the helical coil steam generator. © 2020 American Society of Mechanical Engineers (ASME). All rights reserved.

关键词： Genetic algorithms

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The Instability Marsh Phenomenon and Marginal Stability Boundary Distortion of Density Wave Oscillation in Parallel Channels

SSRN

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SSRN 2024年

作者： Sun, Ducheng Ma, Zaiyong Lu, Q. Liu, C.W. Pan, L.M. School of Energy and Power Engineering Shandong University No. 17923 Jingshi Road Jinan250061 China Key Laboratory of Low-grade Energy Utilization Technologies and Systems Ministry of Education Chongqing400044 China Department of Nuclear Engineering and Technology Chongqing University Chongqing400044 China Science and Technology on Reactor System Design Technology Laboratory Chengdu610041 China

Density wave oscillation (DWO) in parallel channels is an important problem that has been widely studied. The marginal stability boundary (MSB) is often found to be "L " shaped on the N pch -N sub plane, but some very different shapes were also reported. In this paper, the instability marsh region which could occur in the traditional instable region but having both instability and stability sections was presented and discussed, which is found to be an explanation of the distortion of MSB. The analysis of the instability marsh region showed that the evolution of instability marsh should be due to the stability change when operation condition changes, which can be estimated with the analysis of the two-phase and single phase pressure drop variation, as well as Ma’s stability criterion for different heat flux profiles. Variation of instability marsh with different heat flux profile, inlet and outlet resistance coefficient, mass flow and pressure were obtained and analyzed, and the effects of these parameters on instability marsh variation were found to be well interpreted with stability change. The calculation and analysis of instability marsh showed a clear evolution figure of the distortion of MSB under different conditions, and related research could be helpful in better understanding the flow instability in parallel channels. © 2024, The Authors. All rights reserved.

关键词： Stability criteria

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Microstructure and impact toughness of 16MND5 reactor pressure vessel steel manufactured by electrical additive manufacturing

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Journal of Iron and Steel Research International 2020年第8期27卷 992-1004页

作者： Xi-kou He Chang-sheng Xie Li-jun Xiao Ying Luo Di Lu Zheng-dong Liu Xi-tao Wang Institute for Special Steels China Iron and Steel Research InstituteBeijing 100081China Collaborative Innovation Center of Steel Technology University of Science and Technology BeijingBeijing 100083China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu 610041SichuanChina Southern Additive Science and Technology Co. Ltd.Foshan 528225GuangdongChina

Electrical additive manufacturing can improve manufacturing efficiency and reduce the cost of 16MND5 reactor pres-sure vessel steel. Impact tests were conducted to compare the impact toughness of 16MND5 steels manufactured by the electrical additive manufacturing and conventional forging, respectively. It is found that the impact toughness of electrical additive manufacturing specimen was slightly higher than that of conventional forging specimen. The characterizations of microstructure show that there were large ferrites and carbides in electrical additive manufacturing specimen. The fracture mechanisms of electrical additive manufacturing specimen were that microvoids or microcracks were prone to nucleate at the large ferrite/bainite interface and large carbide/bainitic ferrite interface, where the stress concentration was high. In addi-tion, the block size and high-angle grain boundaries played a vital role in hindering crack propagation of electrical additive manufacturing specimen, helping to improve the impact energy and leading to a low ductile–brittle transition temperature. The results suggest that the electrical additive manufacturing technology was an effective method to enhance the impact toughness of 16MND5 steel.

关键词： Electrical additive manufacturing 16MND5 steel Impact toughness Fracture High-angle grain boundary

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