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30th International Conference on Nuclear Engineering, ICONE 2023

作者： Hongcheng, Dong Guangchao, Yang Guo, Chen Xiaofei, Yu Simian, Qin Shanshan, Bu Deqi, Chen Key Laboratory of Low-grade Energy Utilization Technologies and Systems Chongqing University Ministry of Education Chongqing400044 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610200 China

ISBN: (纸本)9784888982566

Helical coil once-through tube steam generator (HCOTSG) has the advantages of compact structure and higher heat transfer efficiency due to its special structure. In order to study the flow boiling heat transfer characteristics in HCOTSG, this paper used the FLUENT commercial software, based on the Critical heat flux(CHF) wall boiling model, to conduct numerical simulation in the spiral tube under the given wall temperature boundary conditions, and verified its reliability by comparing the relevant experimental research. On this basis, the flow boiling heat transfer process in the spiral tube was simulated under different flow parameters, and the velocity field, temperature field and the distribution of vapor-liquid two-phases in the spiral tube were studied, It is found that under the condition of constant wall temperature boundary, the influence of different inlet temperature only exists in the single-phase water region near the inlet, and has little influence on the boiling two-phase region and single-phase steam region. The void fraction decreases at the same height in the boiling two-phase region with the increase of inlet flow velocity, which is due to the decrease of the heating time when the fluid reaches the same height. © 2023 by JSME.

关键词： Heat flux

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Effect of Different Laser Energy Nitriding on the Fretting Wear Performance of Zr Alloy

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摩擦学学报（中英文） 2024年第9期44卷 1306-1321页

作者： NING Chuangming TANG Guocan YU Shijia ZHOU Junbo REN Quanyao ZENG Bing CAI Zhenbing Key Laboratory of Advanced Technologies of Materials Tribology Research InstituteSouthwest Jiaotong UniversitySichuan Chengdu 610031China School of Mechanical and Electrical Engineering Chengdu University of TechnologySichuan Chengdu 610031China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaSichuan Chengdu 610213China

The zirconium(Zr)alloy fuel cladding is one of the key structural components of a nuclear reactor and the first and most important line of defense for accommodating fission *** the operation of nuclear reactors,Zr alloy fuel cladding is subjected to extreme harsh environments,such as high temperature,high pressure and high flow rate for a long period of *** wear and corrosion resistance of Zr alloys is important for the safe operation of nuclear *** modification can effectively improve the corrosion and wear resistance of fuel *** with coating technology,nitriding technology does not have problems for bonding between the coating and the *** research on surface nitriding of Zr alloys mainly focuses on plasma nitriding and ion implantation *** on laser nitriding of Zr alloy surfaces and their fretting wear characteristics is *** this study,the surface of Zr alloy was treated with laser nitriding at different laser *** microstructure of Zr alloy treated with different laser energies and its fretting wear performance were *** results showed that after nitriding with different laser energies,the surface of the Zr alloy showed a typical molten state after melting,vaporizing and cooling under the thermal effect of the laser,and this state was more obvious with the increase of the laser *** the same time,doping of N atoms and formation of the ZrN phase led to different cooling rates in the molten zone that produced large tensile stresses after *** led to cracks on the surface of Zr alloys after laser nitriding at different energies,and the crack density increased with increasing laser *** also led to an increase in the surface roughness of the Zr alloy with increasing laser energy after laser nitriding *** to the presence of water in the industrial nitrogen,nitrides were generated on the surface of the sample along with some *** the laser

关键词： zirconium alloy fretting wear laser nitriding delamination laser energy

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Simulation of Nuclear reactor Accident Scenarios using Physics-Informed Neural Networks and Transfer-Learning 4

Simulation of Nuclear Reactor Accident Scenarios using Physi...

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4th International Conference on Electronic Information Engineering and Computer science, EIECS 2024

作者： Yu, Yang Xie, Yufei Wang, Wenlin Wu, Guohua Lan, Haitao Lin, Enbo An, Ping Sun, Zibin Zhang, Haichuan Wu, Yixian National University of Defense Technology National Key Laboratory of Parallel and Distributed Computing Changsha China Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory Chengdu China School of Automation Wuhan University of Technology Wuhan China Sino-German College of Intelligent Manufacturing Shenzhen Technology University Shenzhen China Institute of Automotive Engineers Hubei University of Automotive Technology Shiyan China Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9798331531409

In a Loss of Coolant Accident (LOCA), reactor core temperatures can rise rapidly, leading to potential fuel damage and radioactive material release. This research presents a groundbreaking method that combines the power of Monte Carlo Sampling and Physics-Informed Neural Networks (PINNs) to simulate and effectively address the challenging Loss of Coolant Accidents (LOCA) in nuclear reactors. In the event of a LOCA, reactor core temperatures can soar rapidly, posing a significant threat to fuel integrity and potentially leading to the release of radioactive materials. By leveraging the strengths of both Monte Carlo Sampling and PINNs, this approach aims to provide a comprehensive and accurate simulation framework for assessing and mitigating the consequences of such accidents. The method yields high prediction accuracy (MAE: 0.033, RMSE: 0.098, R2: 0.814) and demonstrates robustness through transfer learning, maintaining strong performance (MAE: 0.064, RMSE: 0.163, R2: 0.735). © 2024 IEEE.

关键词： Coolants

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Optimization of spatial structure designs of control rod using Monte Carlo code RMC

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Frontiers in Energy 2021年第4期15卷 974-983页

作者： Hao LUO Mancang LI Shanfang HUANG Minyun LIU Kan WANG Department of Engineering Physics Tsinghua UniversityBeijing 100084China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu 610213China CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology China National Nuclear Corporation Nuclear Power Institute of ChinaChengdu 610213China

Control rod is the most important approach to control reactivity in reactors,which is currently a cluster of pins filled with boron carbide(B4C).In this case,neutrons are captured in the outer region,and thus the inner absorber is ***,the lifetime of the control rod is challenged due to the high reactivity worth loss resulted from the excessive degradation of B4C in the high flux *** this work,some control rod designs are proposed with optimized spatial structures including the spatially mixed rod,radially moderated rod,and composite control rod with small-sized *** control rod worth and effective absorption cross section of these designs are computed using the Monte Carlo code RMC.A long-time depletion calculation is conducted to evaluate their burnup *** the spatially mixed rod,rare-earth absorbers are combined with B4C in spatial *** with the homogenous B4C rod,mixed designs ensure more sufficient reactivity worth in the lifetime of the *** minimum reactivity loss at the end of the cycle is only 1.8%from the dysprosium titanate rod,while the loss for pure B4C rod is nearly 12%.For the radially moderated design,a doubled neutronic efficiency is achieved when the volume ratio of moderator equals approximately 0.3,while excessive moderating may lead to the failure of control *** control rod with small-sized pins processes an enhanced safety performance and saves the investment in *** rod worth can be further enhanced by introducing small moderator pins,and the reactivity loss caused by the reduction of absorbers is sustainable.

关键词： control rod optimized spatial structure neutronic performance burnup stability

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Research on Fault Diagnosis Method Based on Structural Causal Model in Tennessee Eastman Process 7th

Research on Fault Diagnosis Method Based on Structural Causa...

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7th International Conference on Computing, Control and Industrial Engineering, CCIE 2023

作者： Pu, Haoyuan Liu, Jie Chen, Zhi Yang, Xiaohua Ren, Changan Xu, Zhuoran Jian, Yifan School of Computer Science University of South China Hengyang China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China Intelligent Equipment Software Evaluation Engineering Technology Research Center of Hunan Hengyang China CNNC Key Laboratory on High Trusted Computing Hengyang China School of Nuclear Science and Technology University of South China Hengyang China

ISBN: (纸本)9789819927296

In the practical application of fault diagnosis in large-scale chemical systems, due to the danger of faults, the machine learning diagnosis methods used in current research often face the problem of scarcity of fault samples. This makes it difficult for the model to be trained effectively, thus affecting the fault detection rate of the model. Therefore, for the fault diagnosis of chemical system with small sample data, this paper proposes a diagnostic method that uses structural causal model to further combine the diagnostic results of the two machine learning methods, thereby improving global diagnostic performance. With the help of powerful system description ability of structural causal model, we can establish a causal graph for diagnostic process of the chemical system, and accurately construct the corresponding structural equations for the various diagnostic results of the two machine learning methods to combine them, thus improve the fault detection rate. The global results make up for the shortcomings of single machine learning method in small sample chemical system fault diagnosis. The verification on the chemical system simulation platform Tennessee Eastman process shows that, compared with the diagnosis results of the selected Gaussian Naive Bayes method and the K-nearest neighbour method, the results obtained by our method are effectively improved in fault detection rate of each fault in TEP. © 2023, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Failure analysis

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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...

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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

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A Mixed-State Particle Filter for Remaining Useful Life Prediction of Lithium-Ion Batteries

SSRN

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SSRN 2024年

作者： Huang, Mengqi Du, Zhengyu Lu, Ruibo Wang, Xiaoji Peng, Changhong School of Nuclear Science and Technology University of Science and Technology of China Anhui Hefei230027 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu610213 China

Lithium-ion batteries are extensively used in medical, transportation, industrial, and other applications due to rapid charging and discharging, constant power output, and light weight. Accurately predicting their remaining useful life (RUL) is essential for safe, reliable operation and timely maintenance. This paper presents a two-stage model based on symbolic regression and particle filter, aims to address the issues present in the current research on lithium-ion battery lifetime prediction. These issues include difficulties in early prediction, using a single degradation model, and the failure to consider the uncertainty of prediction. The proposed model constructs a fuzzy transition point between the two stages based on the degradation process similarity of history and operational batteries. Historical battery degradation data were employed to train the two-stage degradation model using symbolic regression. Parameter updating and state prediction of the degradation model were carried out using an improved mixed-state particle filter. This method can calculate the batteries RUL and their distribution. The performance was evaluated by analysing the CALCE and MIT datasets. The prediction error was less than 22 cycles, over 50% lower than the commonly used FCNN and LSTM timing prediction algorithms, demonstrating the feasibility and effectiveness of the method. © 2024, The Authors. All rights reserved.

关键词： Lithium-ion batteries

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

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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

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

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

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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

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