Volume 4: Student Paper Competition最新文献_第6页

Pipe Performance in Long Term Operation Framework: Ageing Issues 长期运作框架下的管道性能:老化问题

Volume 4: Student Paper Competition Pub Date : 2021-08-04 DOI: 10.1115/icone28-65931

S. A. Cancemi, R. Lo Frano

{"title":"Pipe Performance in Long Term Operation Framework: Ageing Issues","authors":"S. A. Cancemi, R. Lo Frano","doi":"10.1115/icone28-65931","DOIUrl":"https://doi.org/10.1115/icone28-65931","url":null,"abstract":"\u0000 The Long-Term Operation (LTO) process involves a full screening of structures, systems, and components (SSCs), for ageing assessment in order to verify their residual safety margin is still acceptable. At today, 46% of the operating Nuclear Power Plant (NPP) has lifetime between 31 and 40 years, while 19% is in operation since more than 40 years. LTO currently represents the highest priority for all the nuclear industry. To propose and plan suitable management strategies, first step is to intensify the efforts for studying phenomena that influence the performance of SSCs and, in turn, may threat the plant safe operation.\u0000 This study deals with the investigation of the performance of a primary piping (Class 1 component of a 2nd Generation PWR) subjected to the effects of alteration of material properties as caused by ageing. In this study it is proposed a numerical investigation of a piping characterized by a complex geometry. Numerical analyses were performed by means of MSC©MARC FE code. The (quantitative) influence of ageing and corrosion processes onto bent pipe are so studied. Particularly, corrosion effects generated from an operation of beyond 35 years are considered. The methodology and results may have an influence on future issues about LTO of NPPs.","PeriodicalId":108609,"journal":{"name":"Volume 4: Student Paper Competition","volume":"89 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2021-08-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"125101476","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Measurement of Liquid Film Thickness for Annular Two-Phase HFC134a Gas-Liquid Ethanol Flow in the Vertical Tube 垂直管内环空两相HFC134a气液乙醇流液膜厚度的测量

Volume 4: Student Paper Competition Pub Date : 2021-08-04 DOI: 10.1115/icone28-63488

Huacheng Zhang, Tutomo Hisano, S. Mori, H. Yoshida

{"title":"Measurement of Liquid Film Thickness for Annular Two-Phase HFC134a Gas-Liquid Ethanol Flow in the Vertical Tube","authors":"Huacheng Zhang, Tutomo Hisano, S. Mori, H. Yoshida","doi":"10.1115/icone28-63488","DOIUrl":"https://doi.org/10.1115/icone28-63488","url":null,"abstract":"\u0000 Annular gas-liquid two-phase flows, such as the flows attached to the fuel rods of boiling water reactors (BWR), are a prevalent occurrence in industrial processes. At the gas-liquid interface of such flows, disturbance waves with diverse velocity and amplitude commonly arise. Since the thin liquid film between two successive disturbance waves leads to the dryout on the heating surface and limits the performance of the BWRs, complete knowledge of the disturbance waves is of great importance for the characterized properties of disturbance waves. The properties of disturbance waves have been studied by numerous researchers through extensive experimental and analytical approaches. However, most of the experimental data and analyses available in the literature are limited to the near atmospheric condition. In consideration of the properties of liquids and gases under atmospheric pressure which are distinct from those under BWR operating conditions (7 MPa, 285 °C), we employed the HFC134a gas and liquid ethanol whose properties at relatively low pressure and temperature (0.7 MPa, 40 °C) are similar to those of steam and water under BWR operating conditions as working fluids in a tubular test section having an inside diameter 5.0mm. Meanwhile, the liquid film thickness is measured by conductance probes. In this study, we report the liquid film thickness characteristics in a two-phase HFC134a gas-liquid ethanol flow. A simple model of the height of a disturbance wave was also proposed.","PeriodicalId":108609,"journal":{"name":"Volume 4: Student Paper Competition","volume":"40 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2021-08-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"127124265","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 1

Preliminary Version of Improved Particle-Flow Model in SIMMER-V for an Alternative Severe Accident Modeling Approach in SFRs SIMMER-V中改进颗粒流模型的初步版本，用于SFRs严重事故的替代建模方法

Volume 4: Student Paper Competition Pub Date : 2021-08-04 DOI: 10.1115/icone28-64152

Eszter Csengeri, A. Bachratá, L. Trotignon, E. Merle

{"title":"Preliminary Version of Improved Particle-Flow Model in SIMMER-V for an Alternative Severe Accident Modeling Approach in SFRs","authors":"Eszter Csengeri, A. Bachratá, L. Trotignon, E. Merle","doi":"10.1115/icone28-64152","DOIUrl":"https://doi.org/10.1115/icone28-64152","url":null,"abstract":"\u0000 The purpose of the present study is to evaluate and improve the capability of the SIMMER code to demonstrate severe accident mitigation in Sodium-cooled Fast Reactors (SFR). Here the numerical representation of the mitigation strategy with controlled material transfer is carried out with SIMMER. By using the advanced multi-phase modelling option of the code, the particle-size solid debris are treated with an independent momentum field. This modelling choice is encouraged for the simulation of Unprotected Loss Of Flow (ULOF) type transients in French SFR core design where low enthalpy degraded fuel is expected to manifest in solid fragments. Applying this new particulate approach in SIMMER code requires the reevaluation of current SIMMER fluid dynamics modelling. In this context, this paper assesses the applicability of SIMMER momentum models to account for the peculiar behaviour of a purely particulate phase. We present the first improved model of interphase momentum transfer and a sensitivity study on solid particles-wall stress models. The assessment is performed through the investigation of simplified test cases that can be associated to reactor scenarios during severe accident mitigation. The test cases show that the new modifications in the SIMMER code bring significant improvements in predicting the discharge behaviour of degraded core mixture.","PeriodicalId":108609,"journal":{"name":"Volume 4: Student Paper Competition","volume":"3 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2021-08-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"122366751","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Dynamic Modeling of Nuclear Hydrogen Production Using Methane Steam Reforming 甲烷蒸汽重整核制氢动力学建模

Volume 4: Student Paper Competition Pub Date : 2021-08-04 DOI: 10.1115/icone28-64344

Junyi Li, Z. Dong, Bowen Li

引用次数: 0

Heat Transfer and Fluid Flow Characteristic of U-Shaped Flow Channel for Applications of VHTR VHTR应用中u型流道的传热与流体流动特性

Volume 4: Student Paper Competition Pub Date : 2021-08-04 DOI: 10.1115/icone28-64552

Y. Takayama, T. Takeda

{"title":"Heat Transfer and Fluid Flow Characteristic of U-Shaped Flow Channel for Applications of VHTR","authors":"Y. Takayama, T. Takeda","doi":"10.1115/icone28-64552","DOIUrl":"https://doi.org/10.1115/icone28-64552","url":null,"abstract":"\u0000 A very high-temperature reactor (VHTR) is a next-generation nuclear reactor systems. A gas cooling system with natural circulation is considered as a candidate for the pressure vessel cooling system (VCS) of the VHTR. The Japan Atomic Energy Agency is pursuing the design and development of commercial systems such as the 300 MWe gas turbine high-temperature reactor 300 for cogeneration (GTHTR300C). In the VCS of the GTHTR300C, many rectangular flow channels are formed around the reactor pressure vessel (RPV). A cooling panel utilizing the natural convection of air has been proposed. However, the amount of removed heat is inferior to that of cooling by forced convection. In this study, we use an experimental apparatus to simulate the cooling panel of a VCS. The experimental apparatus is a U-shaped flow channel, and the heating surface side is a vertical rectangular flow channel. Air is used as the working fluid. A fine copper wire is used as the porous material. The porosity is varied from 0.996 to 0.999. We perform an experiment to investigate the heat transfer and fluid flow characteristics by natural convection in a vertical rectangular channel heated on one side. Additionally, we perform an experiment on a smooth surface for comparison.","PeriodicalId":108609,"journal":{"name":"Volume 4: Student Paper Competition","volume":"116 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2021-08-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"124061012","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Power Control System Design for a Heat Pipe Cooled Reactor 热管冷却堆功率控制系统设计

Volume 4: Student Paper Competition Pub Date : 2021-08-04 DOI: 10.1115/icone28-64468

Haowei Sun, Peiwei Sun

{"title":"Power Control System Design for a Heat Pipe Cooled Reactor","authors":"Haowei Sun, Peiwei Sun","doi":"10.1115/icone28-64468","DOIUrl":"https://doi.org/10.1115/icone28-64468","url":null,"abstract":"\u0000 Due to the small size, the high-power density and the strong environmental adaptability, the heat pipe cooled reactor has a broad application prospect in the fields of space exploration, underwater vehicle power system and other fields[1]. It will be one of the subversive technologies which will change the future nuclear power development. The safe operation of the heat pipe cooled reactor requires an effective power control system.\u0000 3KeyMaster is a comprehensive real-time simulation analysis platform and the control system can be built by using its logic module. The interface program can be developed in its task program, and other program can be integrated in this platform[2]. The system program of the heat pipe cooled reactor has compiled as a dynamic linking library. Through the task program of the 3KeyMaster simulation platform to call the dynamic linking library by using C++ program, the system program is coupled with the 3KeyMaster simulation platform. The modules of 3KeyMaster platform exchange data with the system program by shared memory.\u0000 Through the responses of the temperature due to step change in the reactor power obtained by 3KeyMaster, the transfer functions are obtained by using the system identification module in MATLAB & Simulink. The power disturbance is introduced, and simulation is carried out on the 3KeyMaster. The changes of the important parameters are analyzed to obtain its dynamic characteristics. Based on the dynamic analysis on the system responses, the control strategy for the power control system is proposed.\u0000 The power control system is implemented in MATLAB & Simulink. The control system parameters are tuned to determine a group of suitable control parameters[3]. Finally, the control performance of power control system is evaluated by simulations.","PeriodicalId":108609,"journal":{"name":"Volume 4: Student Paper Competition","volume":"96 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2021-08-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"130058979","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 1

Research on Remaining Useful Lifetime Prediction Methods of Main Transformer in Nuclear Power Station 核电站主变压器剩余使用寿命预测方法研究

Volume 4: Student Paper Competition Pub Date : 2021-08-04 DOI: 10.1115/icone28-64425

Zikang Li, M. Peng

{"title":"Research on Remaining Useful Lifetime Prediction Methods of Main Transformer in Nuclear Power Station","authors":"Zikang Li, M. Peng","doi":"10.1115/icone28-64425","DOIUrl":"https://doi.org/10.1115/icone28-64425","url":null,"abstract":"\u0000 The main transformer of the NPP is the key equipment connects with public power grid and it is also the important electrical equipment to provide power for the power plant electrical equipment during the shutdown of the generator set. In consequence, it’s failure will cause huge consequences and economic losses. Therefore, the research of reaming life prediction technology for nuclear power plants(NPP) is of great significance to the economic operation and safety of NPP.\u0000 In this paper, according to DL/T984-2005 and other related literature, it is determined that the aging condition of solid insulating fiber material is the main factor to determine the life prediction of transformer. The main aging mechanism of that is summarized, and the effect of temperature is emphatic introduced. In general, the ambient temperature and load curve are the important factors affecting the aging of transformer insulation, furthermore affecting the life of transformer. Therefore, based on GB/T15164-94 recommended ambient temperature and transformer load, this paper calculates the transformer life loss model.\u0000 On this basis, this paper introduces the basic particle filter (PF) and Kalman filter (KF) algorithm flow. Based on the physical formula, a data model is developed to estimate the transformer life loss. Besides, the results are compared and analyzed. The study finally found that there were no significant differences in the accuracy of the predictions. However, considering the fact that the aging of transformer is a monotonic decreasing process, the particle filter based on degradation rate has a slight advantage in life prediction.","PeriodicalId":108609,"journal":{"name":"Volume 4: Student Paper Competition","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2021-08-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"130835867","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Long-Term Simulation of Sodium Dynamics During a Large Leakage Sodium-Water Reaction 大泄漏钠-水反应中钠动力学的长期模拟

Volume 4: Student Paper Competition Pub Date : 2021-08-04 DOI: 10.1115/icone28-64454

Xiao-Yang Bai, Peiwei Sun, Gang Luo, Huasong Cao

{"title":"Long-Term Simulation of Sodium Dynamics During a Large Leakage Sodium-Water Reaction","authors":"Xiao-Yang Bai, Peiwei Sun, Gang Luo, Huasong Cao","doi":"10.1115/icone28-64454","DOIUrl":"https://doi.org/10.1115/icone28-64454","url":null,"abstract":"\u0000 The steam generator of the sodium-cooled reactor is the barrier between the secondary and third loops. When the heat transfer pipe breaks, the water/steam will pour into the sodium and a sodium-water reaction will occur. The pressure in the secondary loop will increase and the rupture disks will burst to reduce the pressure. For the safety analysis, the maximum pressure is limited. For the long term, the pressure pulse weakens and the fluid flow tends to a quasi-steady state several seconds or minutes after leak initiation. Therefore, it is necessary to develop a model to investigate the dynamics of the secondary loop in the long term.\u0000 The continuity equation, the momentum equation and the energy equation are used to derive the sodium flow model in the secondary loop. The sodium pressure and velocity are described by the one-dimensional differential equation. The lumped parameter method is applied and the differential equations are solved by the Euler method. FORTRAN language is compiled to develop the code. Critical equipment, including the steam generator, buffer tank, pump, rupture disks, and accident discharge tank are considered in the secondary loop model. The sodium velocity and pressure responses varying with time can be obtained. Compared with the data from the safety analysis report, the tendency of the sodium velocity and pressure is consistent. It is proved that the model is reasonable and effective to simulate and analyze the actual long-term effects of sodium dynamics.","PeriodicalId":108609,"journal":{"name":"Volume 4: Student Paper Competition","volume":"67 2 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2021-08-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"132657362","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Review of the Configuration Risk Management Methodologies 检讨配置风险管理方法

Volume 4: Student Paper Competition Pub Date : 2021-08-04 DOI: 10.1115/icone28-64281

Yuhang Zhang, Zhijian Zhang, He Wang, Lixuan Zhang, Dabin Sun

{"title":"Review of the Configuration Risk Management Methodologies","authors":"Yuhang Zhang, Zhijian Zhang, He Wang, Lixuan Zhang, Dabin Sun","doi":"10.1115/icone28-64281","DOIUrl":"https://doi.org/10.1115/icone28-64281","url":null,"abstract":"\u0000 To ensure nuclear safety and prevent or mitigate the consequences of accidents, many safety systems have been set up in nuclear power plants to limit the consequences of accidents. Even though technical specifications based on deterministic safety analysis are applied to avoid serious accidents, they are too poor to handle multi-device managements compared with configuration risk management which computes risks in nuclear power plants based on probabilistic safety assessment according to on-going configurations. In general, there are two methodologies employed in configuration risk management: living probabilistic safety assessment (LPSA) and risk monitor (RM). And average reliability databases during a time of interest are employed in living probabilistic safety assessment, which may be naturally applied to make long-term or regular management projects. While transient risk databases are involved in risk monitor to measure transient risks in nuclear power plants, which may be more appropriate to monitor the real-time risks in nuclear power plants and provide scientific real-time suggestions to operators compared with living probabilistic safety assessment. And this paper concentrates on the applications and developments of living probabilistic safety assessment and risk monitor which are the mainly foundation of the configuration risk management to manage nuclear power plants within safe threshold and avoid serious accidents.","PeriodicalId":108609,"journal":{"name":"Volume 4: Student Paper Competition","volume":"218 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2021-08-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"116154787","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Analysis of IP200 Severe Accident Process Response to SBO and Emergency Power Failure IP200严重事故SBO和紧急停电过程响应分析

Volume 4: Student Paper Competition Pub Date : 2021-08-04 DOI: 10.1115/icone28-64541

Z. Zheng, M. Peng, Hao Yu, Yang Yang

{"title":"Analysis of IP200 Severe Accident Process Response to SBO and Emergency Power Failure","authors":"Z. Zheng, M. Peng, Hao Yu, Yang Yang","doi":"10.1115/icone28-64541","DOIUrl":"https://doi.org/10.1115/icone28-64541","url":null,"abstract":"\u0000 Advanced SMRs such as the integrated pressurized water reactor IP200 use different design in the systems, structures, components from large reactors for achieving a high level of safety and reliability. In this thesis, the IP200 severe accident induced by the SBO and emergency power failure was modeled and analyzed using RELAP5 / SCDAP / MOD3.4 code. Based on the steady state calculation, which agrees well with designed values, the SBO accident for transient calculation is carried out. First, the case of the SBO accident without the passive core cooling system was calculated. The progression and scenario in the RPV was simulated and analyzed, including the transient response, cooling capacity and thermal-hydraulic characteristics and so on. Then, mitigation measures PRHRS and CMT were put in at four different time points when the core is began to uncovered, the core is completely uncovered, hydrogen is began to produced, and the molten pool is formed. The results show that putting in mitigation measures before the accident progresses to the point where the core starts to produce hydrogen can ensure that the core does not melt and avoid hydrogen risk.","PeriodicalId":108609,"journal":{"name":"Volume 4: Student Paper Competition","volume":"10 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2021-08-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"127549437","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0