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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 Monte Carlo Code Developed for Radiation Shielding Calculations Based on RMC 23rd

A Monte Carlo Code Developed for Radiation Shielding Calcula...

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23rd Pacific Basin Nuclear Conference, PBNC 2022

作者： Ying, Dongchuan Lyu, Huanwen Tang, Songqian Shang, Xiaotong Xiao, Feng National Key Laboratory of Reactor System Design Technology Nuclear Power Institute of China Chengdu610041 China Department of Engineering Physics Tsinghua University Beijing100084 China

ISBN: (纸本)9789811988981

In this paper, a new developed Monte Carlo method code, intended to be used in shielding calculations, will be introduced. This code was developed on the basis of RMC and under the collaboration of the Nuclear Power Institute of china and Tsinghua University. To meet the requirement of shielding calculations, many features or functions have been realized, such as the flexible fixed source definition and calculation, the gamma transport function, variance reduction function and various tally functions, etc. Those functions have enabled the new version of RMC to have the radiation shielding capability. The validation and application of radiation shielding calculation capability have been carried out. The results of a nuclear power plant pressurized water reactor model will be presented and good agreements have been achieved, which proves the capability of the RMC in the shielding calculations. © 2023, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Pressurized water reactors

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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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A Cost-Sensitive Multi-scale Feature Multi-order Fusion Network for Bearing Fault Diagnosis Under Data Imbalance Conditions

A Cost-Sensitive Multi-scale Feature Multi-order Fusion Netw...

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International Conference on Artificial Intelligence and Autonomous Transportation, AIAT 2024

作者： Deng, Shuaiqing Lei, Zihao Wen, Guangrui Su, Yu Liu, Zimin Meng, Zhangxuan Zhang, Zhifen National Key Laboratory of Aviation Power System and Plasma Technology Xi’an Jiaotong University Xi’an710049 China State Key Laboratory for Manufacturing Systems Engineering Xi’an Jiaotong University Xi’an710049 China Key Laboratory of Education Ministry for Modern Design and Rotor-Bearing System Xi’an Jiaotong University Xi’an710049 China

ISBN: (纸本)9789819639724

Railroad transportation plays a vital role in the national economy, and fault diagnosis of its key components is of great significance in ensuring its safe operation. However, due to its long-term operation in a healthy state, it is tough to obtain fault signals, and this class imbalance data seriously degrades the diagnostic capability of intelligent diagnostic algorithms, leading to increased misclassification of minority classes. To address this problem, we propose a cost-sensitive multi-scale feature multi-order fusion network for bearing fault diagnosis under data imbalance conditions. Firstly, a lightweight multi-scale convolutional layer is employed to effectively extract the multi-scale features of the signal. Then the multi-order feature fusion is performed by a hornet to fully utilize the multi-scale information and enhance the ability to mine the limited diagnostic information of the minority class. And the excellent high-dimensional discriminative features are extracted through residual blocks. In addition, an improved cost-sensitive strategy is designed through the posterior probability distribution to rebalance the contribution of each class to the training process for improving the overall diagnostic performance of the model. Finally, the effectiveness and superiority of the proposed method are comprehensively verified by several sets of experiments with different imbalance rates. © Beijing Paike Culture Commu. Co., Ltd. 2025.

关键词： Railroad transportation

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MSC-APFNN: Fault Diagnosis Deep Transfer Network for Rotating Machine based on Multi-scale Convolutional Extraction and Adaptive Pruning Fuzzy Inference system

MSC-APFNN: Fault Diagnosis Deep Transfer Network for Rotatin...

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International Conference on Artificial Intelligence and Autonomous Transportation, AIAT 2024

作者： Zhou, Yanrun Lei, Zihao Wen, Guangrui Su, Yu Zhang, Zhifen National Key Lab of Aerospace Power System and Plasma Technology Xi’an Jiaotong University Xi’an710049 China State Key Laboratory for Manufacturing Systems Engineering Xi’an Jiaotong University Xi’an710049 China Key Laboratory of Education Ministry for Modern Design and Rotor-Bearing System Xi’an710049 China

ISBN: (纸本)9789819639687

Intelligent fault diagnosis on mechanical transmission system of the train is of great importance to ensure the efficient operation of high-speed trains. However, due to the complex and changeable operation conditions (OCs), it is difficult to ensure the uniformity of the data distribution obtained by real-time acquisition, which sets a higher standard for the design of intelligent algorithms. Empowered by deep transfer learning (DTL) methods, the fuzzy inference system provides an effective solution to the abovementioned problem. In this paper, an Adaptive Pruning Fuzzy Inference system (APFIS) is proposed predicated on the fuzzy theory and the basic structure of fuzzy neural network, along with the hybrid model MSC-APFNN constructed by combining the multi-scale convolutional network with the proposed APFIS. This model can be employed as a backbone for the application to transfer diagnostic detection of rotating systems based on adversarial networks. Experimental results demonstrate that the proposed model achieves excellent diagnostic results under variable operating conditions, which provide a novel insight into the optimization of the traditional convolutional and fully-connected deep network structure and offer a promising avenue for the research of fuzzy decision-making in the context of fault diagnostics for high-speed trains. © Beijing Paike Culture Commu. Co., Ltd. 2025.

关键词： Fuzzy neural networks

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THE DEVELOPMENT OF FISSION PRODUCT DIFFUSION/RELEASE MODEL FOR FAILED TRISO PARTICLES 30

THE DEVELOPMENT OF FISSION PRODUCT DIFFUSION/RELEASE MODEL F...

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30th International Conference on Nuclear Engineering, ICONE 2023

作者： Zheng, Junqiang He, Yanan Wu, Junmei Wu, Yingwei Li, Yuanming Tian, Wenxi Su, Guanghui Qiu, Suizheng School of Nuclear Science and Technology Xi'an Jiaotong University Xi'an China State Key Laboratory for Strength and Vibration of Mechanical Structures School of Aerospace Xi'an Jiaotong University Xi'an China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institution of China Chengdu China

ISBN: (纸本)9784888982566

TRISO coated fuel particle has been adopted in the design of various reactors and Accident Tolerant Fuel (ATF) due to its excellent accident tolerant performance under high temperatures and other severe conditions. Accurately estimating fission product release from TRISO-coated fuel particles is indispensable to calculate the mechanistic source term. In most models, a bare kernel is substituted conservatively for failed particle. Thus, a theoretical method was proposed to describe the transport of fission products in intact and failed fuel particles. In this paper, to analyze the diffusion and release characteristics of intact TRISO-coated fuel particles' fission products, the fission products diffusion model of TRISO-coated fuel particles with thermal-mechanical coupling was established based on the COMSOL Multiphysics software and verified by the IAEA CRP-6 benchmark. The results indicate that the predictions by the developed fission product transport model is reasonable. Moreover, to analyze fission product release for failed partials, a conceptual theoretical method was proposed. The adsorption and desorption constraint model for fission products at the gas-solid interface and the gas phase diffusion model were added to the original model to analyze. Subsequently, predictions comparison for fission products' fractional release in failed particles between the proposed method and the Settings adopted in BISON were completed. The result suggests that the gas-phase diffusion model is feasible and seems favorable to simulate the diffusion of fission products in the failed coating layers. © 2023 by JSME.

关键词： Fission products

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EXPERIMENTAL STUDY ON FLOW-INDUCED VIBRATION CHARACTERISTICS OF A SINGLE ROD IN AXIAL FLOW 30

EXPERIMENTAL STUDY ON FLOW-INDUCED VIBRATION CHARACTERISTICS...

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30th International Conference on Nuclear Engineering, ICONE 2023

作者： Pu, Xingwu Chen, Deqi Liu, Hanzhou Wang, Ningyuan Zi, Binbin Deng, Jian 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 Chengdu610041 China

ISBN: (纸本)9784888982566

In order to study the characteristics of single rod flow-induced vibration in axial flow, the vibration response of single rod flow-induced vibration in axial flow with different constraints at both ends and different flow velocity was measured with a Laser Doppler Vibrometer. Based on spectral analysis and statistical analysis, the transient vibration response was analyzed in depth. The results show that the vibration amplitude increases with the increase of the flow velocity, and the two ends of the constraints have a significant influence on the flow-induced vibration response. The root means square amplitude value of the simply-supported single rod is 35% larger than that of the fixed one at 3 m/s. Spectrum analysis shows that with the increase of flow velocity, the dominant frequency decreases from 17.5 Hz at 1.5 m/s to 13.8 Hz at 3.0 m/s under simply-supported constraints, while the dominant frequency basically fluctuates around 13.0 Hz under fixed support constraints. The vibration frequency of simply-supported constraints are distributed between 6 Hz and 28 Hz, while those of fixed constraints are mainly distributed between 12 Hz and 16 Hz. The statistical results show that in the X direction of the simply-supported constraints, the geometric center point of the rod is shifted, which indicates that the rod is buckling. © 2023 by JSME.

关键词： Nuclear reactors

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CFD simulation of thermal hydraulic characteristics in a typical upper plenum of RPV

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Frontiers in Energy 2021年第4期15卷 930-945页

作者： Mingjun WANG Lianfa WANG Yingjie WANG Wenxi TIAN Jian DENG Guanghui SU Suizheng QI State Key Laboratory of Multiphase Flow in Power Engineering Department of Nuclear Science and TechnologyXi’an Jiaotong UniversityXi’an 710049China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu 610213China

A comparative computational fluid dynamics(CFD)study was conducted on the three different types of pressurized water reactor(PWR)upper plenum,named TYPE 1(support columns(SCs)and control rod guide tubes(CRGTs)with two large windows),TYPE 2(SCs and CRGTs without windows),and TYPE 3(two parallel perforated barrel shells and CRGTs).First,three types of upper plenum geometry information were collected,simplified,and adopted into the BORA facility,which is a 1/5 scale system of the four-loop PWR ***,the geometry,including the upper half core,upper plenum region,and hot legs,was built using the Salome *** that,an unsteady calculation to simulate the reactor balance operation at hot full power scenario was ***,the differences of flowrate distribution at the core outlet and temperature distribution and transverse velocity inside the hot legs with different upper plenum internals were *** results suggest that TYPE 1 upper plenum internals cause the largest flowrate difference at the core outlet while TYPE 3 leads to the most even distributed *** distribution and evolution pattern of the tangential velocity inside hot legs is highly dependent on the upper plenum *** counter-rotating swirls exist inside the TYPE 1 hot leg and only one swirl revolving around the hog leg axis exist inside the TYPE 2 hot *** TYPE 3,two swirls like that of TYPE 1 rotating around the hot leg axis significantly increase the temperature homogenization *** research provides meaningful guidelines for the future optimization and design of advanced PWR upper plenum internal structures.

关键词： pressurized water reactor(PWR) upper plenum internal structures temperature distribution computational fluid dynamics(CFD)

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NUMERICAL SIMULATION OF THERMAL CHARACTERISTICS OF BOILING TWO-PHASE FLOW IN A SPIRAL TUBE 30

NUMERICAL SIMULATION OF THERMAL CHARACTERISTICS OF BOILING T...

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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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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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