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2024 31st International Conference on Nuclear Engineering, ICONE 2024

作者： Yugao, Ma Jiahao, Lu Yue, Liu Suyi, Zhang Muhao, Zhang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China College of Nuclear Technology and Automation Engineering Chengdu University of Technology Chengdu610059 China

ISBN: (纸本)9780791888247

The Fission Surface Power system is a feasible solution for future lunar surface exploration energy supply, with the solid-state reactor being considered a primary candidate. This paper presents a modeling and analysis of a solid-state reactor based on publicly available information. Using the reactor Monte Carlo program RMC and the commercial finite element analysis software ANSYS, the reactor is modeled and analyzed. The power distribution of the active zone and reactivity feedback coefficients of the entire core are obtained. The result indicates a negative reactivity feedback coefficient, confirming this reactor design's inherent safety. Furthermore, a two-dimensional reactor model is constructed to obtain the temperature distribution during full-power operation, and non-passive residual heat removal analysis and radiative heat loss failure analysis are performed. At the failure condition of all heat pipes, the maximum core temperature is 742 K, which is below the reactor safety temperature limit, confirming the residual heat removal capability of the solid-state reactor in the loss of heat sink. Additionally, the self-developed transient reactor system analysis program is used for thermal safety analysis. The thermal parameters and heat transfer limits of high-temperature alkali metal heat pipes within the reactor are obtained, with the ratio of heat transfer limit to the heat load of 2.05 demonstrating sufficient safety margins of the heat pipe operation in the reactor. The results manifest that the core is satisfied with the existing criteria for anticipated operating occurrences of solid-state reactors, verifying the excellent safety performance of this reactor design. Based on the analysis and calculations in this study, it is concluded that this reactor design exhibits superior safety performance, which is attributed to the neutron physics design concept of the intermediate neutron spectrum and the thermal-hydraulic design concept of non-passive residual h

关键词： Lunar surface analysis

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Fault Severity Classification based on Information Flow and Support Vector Machines 8

Fault Severity Classification based on Information Flow and ...

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8th International Conference on Energy system, Electricity, and Power, ESEP 2023

作者： Yang, Xiaohua Liu, Zhikun Fang, Weiyang Huang, Tao Liu, Jie Yang, Jinghua Ren, Changan Department of Compute Science University of South China Hengyang421001 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China

ISBN: (数字)9781510679801

ISBN: (纸本)9781510679795

Fault severity describes the level of impact caused by a fault. In the event of a malfunction in a nuclear power plant, a vast amount of data and alarms are generated, making it challenging for operators to identify and determine the state of the power plant in a short time. If the fault severity can be effectively identified during a malfunction, it would allow the operators to respond quickly and prevent further losses. Compared to other machine learning methods, the Support Vector Machine (SVM) has superior classification capability in scenarios with limited nuclear power samples. However, if the feature representation of the SVM training sample is inadequate, resulting in similar, indistinguishable training data, it will affect the SVM's classification of fault severity. To address this issue, using the Liang-Kleeman Information Flow (IF) can characterize information transmission from a causal perspective. By introducing IF to combine features of the training data, insufficient sample features can be replaced with the IF that describes information from a causal viewpoint, thereby enhancing the SVM's accuracy in fault severity classification. This paper takes the Main Steam Line Break accident in the primary loop of the nuclear reactor as an example and conducts simulation experiments on the PCTRAN simulation platform. The experimental results show that under 5 different fault degrees, the accuracy of fault degree evaluation of SVM model combined with IF is improved. This method can effectively improve the classification accuracy of different fault severity degrees in MSLB steam flow data with similar changes. © 2024 SPIE.

关键词： Steam piping systems

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THE STUDY of COUPLED FUEL PERFORMANCE ANALYSIS and NEUTRONICS with COMSOL and RMC 29

THE STUDY of COUPLED FUEL PERFORMANCE ANALYSIS and NEUTRONIC...

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2022 29th International Conference on Nuclear Engineering, ICONE 2022

作者： Liu, Zhenhai Qi, Feipeng Zhou, Yi Li, Quan Chen, Ping Chen, Hao Ma, Chao Zhao, Bo Li, Chenxi Science and Technology on Reactor System Design Technology Laboratory Npic Chengdu China

ISBN: (纸本)9780791886366

Predicting fuel behavior in the reactor is a typical multiphysics coupling problem. The traditional fuel performance analysis adopts a decoupling way. To provide a higher fidelity tool for fuel performance simulation, the multi-physics coupling software COMSOL and 3D Monte Carlo neutron transport code RMC are coupled. The fuel rod thermo-mechanical coupling analysis module is constructed in COMSOL. RMC is innovatively wrapped as a component of COMSOL to communicate with the fuel performance module. Grid mapping algorithm is set up using COMSOL's functionality. A carefully designed segregation solver sequence is used to control the coupling process. The fine power distribution calculated by RMC is transferred to COMSOL fuel thermal calculation, and the fuel temperature and the coolant temperature and density calculated by COMSOL are transferred to RMC. In a Picard iterative way, the fuel rod lattice level neutron thermomechanical tight coupling is realized. The coupling is demonstrated in a fuel rod BOL steady state case. The fuel performance analysis is enhanced by the higher fidelity neutron flux solution. © 2022 American Society of Mechanical Engineers (ASME). All rights reserved.

关键词： Iterative methods

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REVIEW OF RISK-INFORMED SAFETY design CONCEPT, METHOD AND APPLICATION 30

REVIEW OF RISK-INFORMED SAFETY DESIGN CONCEPT, METHOD AND AP...

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30th International Conference on Nuclear Engineering, ICONE 2023

作者： Gong, Lanxin Zhong, Mingjun Peng, Changhong School of Nuclear Science and Technology University of Science and Technology of China Hefei China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9784888982566

Since the NRC issued the PSA policy in 1995, PSA containing risk information has been widely used in supervision and design. Subsequently, the concept of "risk-informed" has gained more and more recognition, and its application has expanded from the initial equipment maintenance to the current design. By analyzing the regulations, standards and other guidance documents of various countries and institutions on safety design, we reviewed the history of risk-informed safety design concepts, methods and their applications, especially the progress of LMP projects in the United States in recent years. We put forward prospects for the development and application of risk-informed concepts and methods in new reactors in the future. © 2023 by JSME.

关键词： design

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RESEARCH ON INTEGRATED VIBRATION ISOLATION AND VIBRATION ABSORPTION FOR PUMP EQUIPMENT 30

RESEARCH ON INTEGRATED VIBRATION ISOLATION AND VIBRATION ABS...

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30th International Congress on Sound and Vibration, ICSV 2024

作者： Zhaowen, Li Longqi, Cai Yu, Wang Lizhi, Liu Jianyong, Lai National Key Laboratory of Reactor System Design Technology Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9789090390581

Pump equipment is the main source of vibration and noise during ship operation, and there are distinct characteristic line spectra at various transmission paths, which is not conducive to vibration reduction and noise control of ship system. Therefore, this paper focuses on a type of pump with significant vibration and prominent 50Hz characteristic line spectrum. It conducts research on integrated vibration isolation and vibration absorption based on floating raft isolation and dynamic vibration absorbers. The feasibility of above scheme was verified by the research on floating raft structure design, research on dynamic vibration absorber parameters, and analysis of vibration reduction and absorption effects. This paper provides a great measure to reduce the delivery of vibration and control line spectrum feature of one frequency of pump equipment. © 2024 Proceedings of the International Congress on Sound and Vibration. All rights reserved.

关键词： Vibration analysis

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A Transformer-based Time Series Prediction Model with Contrastive Learning for Nuclear Power system State Monitoring 15

A Transformer-based Time Series Prediction Model with Contra...

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

作者： Gou, Pengfei Zheng, Daiwei Tang, Lei Liu, Mengjuan School of Information and Software Engineering University of Electronic Science and Technology of China UESTC Chengdu China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China NPIC Chengdu China

ISBN: (纸本)9798350354010

Prognostics and Health Management (PHM) is currently the mainstream solution for the condition monitoring and maintenance of industrial systems. In PHM, the system condition is monitored by monitoring the operational status parameters of the system to diagnose equipment faults, predict the remaining useful life, etc. Utilizing sequential operational status parameters to complete prediction and classification tasks is usually modeled as a time series processing task. Therefore, a high-performance time series prediction model is crucial for PHM. This paper focuses on the use of time series prediction models to achieve the prediction of key state parameters of the nuclear power system. However, there are still some challenges when directly applying existing time series prediction models to industrial systems. First, obtaining operational data on the nuclear power system is relatively difficult, resulting in a small amount of training data, which causes many models to face the risk of insufficient training or overfitting. Second, most of the existing time series prediction models are composed of high- and low-frequency decoupling modules, while the operational data of nuclear power systems often have fewer high-frequency components, making it difficult for many existing SOTA models to achieve good results. In order to address these challenges, we have developed a Transformer-based time series prediction model with contrastive learning for monitoring the status of nuclear power systems. We evaluated the new model on three nuclear power simulation datasets and four power transformer datasets. The experimental results show that the new model's performance is superior to baseline models. We also proved the effectiveness of our improvement through ablation experiments. © 2024 IEEE.

关键词： Prediction models

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Research on model validation of routing protocol for UAV swarm cooperative disaster relief system

Research on model validation of routing protocol for UAV swa...

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2023 International Conference on Computer Application and Information Security, ICCAIS 2023

作者： Wei, Tonghao Liu, Jie Yang, Fei Han, Wenxing Jiang, Wei School of Computer Science/Software University of South China Hunan Hengyang China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China

ISBN: (纸本)9781510675032

In recent years, with the continuous expansion of unmanned aerial vehicle (UAV) swarm applications and the rapid development of the UAV self-organizing network system, the related security threats have also increased. In this paper, we conduct the communication model of the UAV swarm cooperative disaster relief system by verifying the security attributes of the UAV swarm cooperative disaster relief system based on the dynamic source routing (DSR) protocol and we also analyze and verify their security attributes. Finally, we propose a novel scheme to model, characterize, and verify the security attributes of the UAV swarm communication networks. It provides a formal analysis and verification method for verifying the security attributes of self-organized network systems, simplifying a series of challenging verification processes that come with demonstrating the security attributes of the system through simulation experiments. © 2024 SPIE.

关键词： Formal verification

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Research on Output Torque Optimization of Ultrasonic Motor Based on Genetic Algorithm 17th

Research on Output Torque Optimization of Ultrasonic Motor B...

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17th Annual Conference of China Electrotechnical Society, CES 2022

作者： Li, Xiaoyang Tang, Jiankai Yang, Bo Wu, Hao Xu, Qiwei Yang, Yun The State Key Laboratory of Power Transmission Equipment & System Security and New Technology Chongqing University Chongqing400030 China Science and Technology on Reactor System Design Technology Laboratory Chengdu610041 China

ISBN: (纸本)9789819904501

Aiming at the problem of small output torque in the design process of traveling to wave ultrasonic motor, this paper proposes a method of optimizing the output torque of traveling to wave ultrasonic motor based on multi-objective genetic algorithm. It can effectively improve the output torque of the motor. Firstly, the structure and operation mechanism of the motor is introduced, and the key factors affecting the output torque of the motor is analyzed reasonably;then the parameterized model of the stator of the ultrasonic motor is established by WORKBENCH, the sample points are randomly selected in the design variable space, and the combination of each sample point is obtained. The modal analysis and harmonic response analysis of the stator structure was carried out to establish the response surfaces model of the stator;finally, the global optimal solution was obtained based on the response surface model by using the multi-objective genetic algorithm (MOGA). The results show that the output torque of the ultra-sonic motor can be increased by 8% before and after optimization. © 2023, Beijing Paike Culture Commu. Co., Ltd.

关键词： Stators

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Modeling of Mesoscale Creep Behaviors and Macroscale Creep Responses of Composite Fuels Under Irradiation Conditions

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Acta Mechanica Solida Sinica 2022年第6期35卷 1040-1054页

作者： Jing Zhang Jingyu Zhang Haoyu Wang Changbing Tang Pan Yuan Chunyu Yin Shurong Ding Yuanming Li Institute of Mechanics and Computational Engineering Department of Aeronautics and AstronauticsFudan UniversityShanghai200433China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu610213China

A finite-strain homogenization creep model for composite fuels under irradiation conditions is developed and verified,with the irradiation creep strains of the fuel particles and matrix correlated to the macroscale creep responses,excluding the contributions of volumetric strain induced by the irradiation swelling deformations of fuel particles.A finite element(FE)modeling method for uniaxial tensile creep tests is established with the irradiation effects of nuclear materials taken into *** proposed models and simulation strategy are numerically implemented to a kind of composite nuclear fuel,and the predicted mesoscale creep behaviors and the macroscale creep responses are *** research results indicate that:(1)the macroscale creep responses and the mesoscale stress and strain fields are all greatly affected by the irradiation swelling of fuel particles,owing to the strengthened mechanical interactions between the fuel particles and the matrix.(2)The effective creep rates for a certain case are approximately two constants before and after the critical fission density,which results from the accelerated fission gas swelling after fuel grain recrystallization,and the effects of macroscale tensile stress will be more enhanced at higher temperatures.(3)The macroscale creep contributions from the fuel particles and matrix depend mainly on the current volume fractions varying with fission density.(4)As a function of the macroscale stress,temperature,initial particle volume fraction and particle fission rate,a multi-variable mathematical model for effective creep rates is fitted out for the considered composite fuels,which matches well with the FE *** study supplies important theoretical models and research methods for the multi-scale creep behaviors of various composite fuels and provides a basis for simulation of the thermal–mechanical behavior in related composite fuel elements and assemblies.

关键词： Composite fuels Effective irradiation creep rate model Homogenization creep theory Irradiation swelling Large deformation

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Modeling of irradiation-induced damage and failure behaviors of fuel foil/cladding interface in UMo/Zr monolithic fuel plates

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Nuclear science and Techniques 2022年第5期33卷 16-29页

作者： Xiang-Zhe Kong Xiao-Bin Jian Feng Yan Chang-Bing Tang Zi-Xuan Guo Shu-Rong Ding Yuan-Ming Li Chun-Yu Yin Institute of Mechanics and Computational Engineering Department of Aeronautics and AstronauticsFudan UniversityShanghai 200433China Science and Technology On Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu 610213China

Models to describe the damage and fracture behaviors of the interface between the fuel foil and cladding in UMo/Zr monolithic fuel plates were established and numerically *** effects of the interfacial cohesive strength and cohesive energy on the irradiationinduced thermal-mechanical behaviors of fuel plates were *** results indicated that for heterogeneously irradiated fuel plates:(1)interfacial damage and failure were predicted to be initiated near the fuel foil corner with higher fission densities,accompanied by the formation of a large gap after interface failure,which was consistent with some experimental observations;high tensile stresses in the fuel foil occurred near the edges of the failed interface,attributed to through-thickness cracking of the fuel foil,as found in some post-irradiation examinations;(2)the cohesive strength and cohesive energy of the interface both influenced the in-pile evolution behaviors of fuel plates;a lower cohesive strength or cohesive energy resulted in faster interfacial damage;(3)after interface fracture,the thickness of the whole plate increased to a greater degree(by~20%)than that of the samples without interfacial damage,which was attributed to the locally enhanced Mises stresses and the nearby creep deformations around the cracked *** study provided a theoretical basis for assessing failure in fuel elements.

关键词： UMo/Zr Irradiation-inducedthermo-mechanicalbehavior Numericalsimulation Cohesive model Interfacialfailure

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