Volume 5: Nuclear Safety, Security, and Cyber Security最新文献_第5页

Research on Radionuclide Diffusion and Verification in the Ocean Under Nuclear Leakage Accidents 核泄漏事故下海洋放射性核素扩散与验证研究

Volume 5: Nuclear Safety, Security, and Cyber Security Pub Date : 2022-08-08 DOI: 10.1115/icone29-89256

Zichao Li, Rong-chang Chen, Qingqing Xue, Chen Liu, Zhixia Wang, Tao Zhou

{"title":"Research on Radionuclide Diffusion and Verification in the Ocean Under Nuclear Leakage Accidents","authors":"Zichao Li, Rong-chang Chen, Qingqing Xue, Chen Liu, Zhixia Wang, Tao Zhou","doi":"10.1115/icone29-89256","DOIUrl":"https://doi.org/10.1115/icone29-89256","url":null,"abstract":"\u0000 All operational and under construction nuclear power plants in China are distributed in coastal areas presently. Facing the problem of spent fuel from nuclear reactors, we are also actively promoting the system construction of combined transport with highway, ocean and railway. In case of nuclear leakage accidents, radionuclides will diffuse through the ocean and pollute the ecological environment. The study of radionuclide diffusion and verification in the ocean plays an important role under nuclear leakage accidents. The hydrodynamic model and radionuclide diffusion model in coastal waters of nuclear power plant were established. The water level change and radionuclide diffusion area in coastal waters of nuclear power plant were calculated, and dangerous areas were given. The calculated results were verified by enteromorpha drift. The results show that radioactivity in the high concentration area can reach 109Bq/m3, and it is reduced by about 9 orders of magnitude to the source term. On the 14th day, the dangerous area is within about 58km to the east, 10km to the south and 21km to the west of the nuclear power plant. In the east-west direction, the dangerous area is about half of the radionuclide diffusion area.","PeriodicalId":365848,"journal":{"name":"Volume 5: Nuclear Safety, Security, and Cyber Security","volume":"141 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"133057629","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

Study of the Regular Pattern Between the Geometric Characteristics of Radioactive Package and Its External Radiation Dose Rate 放射性包装几何特性与其外辐射剂量率的规律研究

Volume 5: Nuclear Safety, Security, and Cyber Security Pub Date : 2022-08-08 DOI: 10.1115/icone29-93641

Zhipeng Wang, Changwu Wang, Qian Sun, Yuhang Zhang, Lei Chen

{"title":"Study of the Regular Pattern Between the Geometric Characteristics of Radioactive Package and Its External Radiation Dose Rate","authors":"Zhipeng Wang, Changwu Wang, Qian Sun, Yuhang Zhang, Lei Chen","doi":"10.1115/icone29-93641","DOIUrl":"https://doi.org/10.1115/icone29-93641","url":null,"abstract":"\u0000 In recent years, as an important part of the nuclear technology used in the fields of industry, agriculture, medicine and scientific research, the transportation of radioactive materials has increased rapidly. diversification trend. In order to ensure the safety of relevant staff and the public, countries around the world and the IAEA have made certain regulations and constraints on the external radiation rates of radioactive material transport packages. Taking China as an example, <The Regulations for the Safe Transport of Radioactive Materials> (GB11806-2019) is a national mandatory standard specially formulated in accordance with relevant national laws and regulations to prevent radioactive pollution, improve environmental quality, and regulate the management of radioactive materials transportation. The safety requirements for the transport of radioactive materials under normal transport conditions and transport accident conditions, in which the dose rates on the outer surface of the radioactive material package and at 1m are clearly specified. In practical work, it is often necessary to evaluate the surface of the package at different positions and the dose rate at 1m to ensure transportation safety. Based on several radioactive material transport containers with mature experience, this paper calculates the external radiation levels of various shapes of packages by using mathematical methods, and classifies them according to the geometric characteristics of the containers and the distribution of the contents. The influence of the surface of the location and the variation law of the dose rate at 1m is analyzed to provide a reference for the radiation safety management of radioactive material transportation activities.","PeriodicalId":365848,"journal":{"name":"Volume 5: Nuclear Safety, Security, and Cyber Security","volume":"40 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"116622607","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

Experimental Study on Structural Vibration Characteristics of Single Rod in Different Flow States of Water 不同水流状态下单杆结构振动特性的实验研究

Volume 5: Nuclear Safety, Security, and Cyber Security Pub Date : 2022-08-08 DOI: 10.1115/icone29-91975

Yibo Yin, Jiming Wen, Xinyang Yu, Xin Li, P. Gao, Ruifeng Tian, Junshuai Sun

{"title":"Experimental Study on Structural Vibration Characteristics of Single Rod in Different Flow States of Water","authors":"Yibo Yin, Jiming Wen, Xinyang Yu, Xin Li, P. Gao, Ruifeng Tian, Junshuai Sun","doi":"10.1115/icone29-91975","DOIUrl":"https://doi.org/10.1115/icone29-91975","url":null,"abstract":"\u0000 In the nuclear reactor, flowing state of surrounding fluid will change structural vibration characteristics of fuel rods, which may lead to severe resonance and damage of fuel rods. Therefore, it is necessary to study structural vibration characteristics of fuel rods in different fluid flow states. In this paper, based on experiment, structural vibration characteristics of a single rod in different water flow states and different restraint modes are obtained by hammering method. The results show that different restraint modes have influence on dry mode, wet mode and structural vibration characteristics of the rod. Under condition of no excitation, when flow rate is lower than 1m/s, the response frequency and flow velocity change trend is the same under different restraint modes, response frequency of test rod with increases of flow rate. When flow rate is more than 1m/s, the response frequency varies with flow rate in different restraint modes. Under the fixed support, the excitation ways and excitation positions have no effect on natural frequency of rod. For simply supported, the excitation positions have great influence on the natural frequency of rod. It has reference significance for the safety design of fuel rods.","PeriodicalId":365848,"journal":{"name":"Volume 5: Nuclear Safety, Security, and Cyber Security","volume":"25 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"116090898","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

Study on the Added Mass of the Double-Fixed Constrained Flexible Coaxial Cylindrical Shells With Liquid in the Narrow Gap 窄间隙含液双固定约束同轴柔性圆柱壳的附加质量研究

Volume 5: Nuclear Safety, Security, and Cyber Security Pub Date : 2022-08-08 DOI: 10.1115/icone29-92137

Dong Li, D. Lu, Yuxuan Zhu, Yu Liu

{"title":"Study on the Added Mass of the Double-Fixed Constrained Flexible Coaxial Cylindrical Shells With Liquid in the Narrow Gap","authors":"Dong Li, D. Lu, Yuxuan Zhu, Yu Liu","doi":"10.1115/icone29-92137","DOIUrl":"https://doi.org/10.1115/icone29-92137","url":null,"abstract":"\u0000 There are many coaxial cylindrical thin-wall structures with a narrow fluid gap in the reactor block of the pool type sodium cold fast reactor (such as primary pump support and its thermal shield). The fluid-structure interaction (usually represented by added mass) of shells and the fluid gap changes the structure’s dynamic characteristics under seismic conditions. Therefore, it is significant to calculate the added mass of the coaxial cylindrical shells. At present, there are few studies on the vibration modes and added mass of flexible shells with double-fixed constrain. For the flexible coaxial cylindrical shells model, due to the coupling of the inner and outer shell, the vibration modes of the inner and outer shell in the same and opposite directions are generated. In this paper, the added mass of two vibration modes in the same direction and in the opposite direction are investigated. The finite element models (with water and without water) of the coaxial cylindrical shells were established using ANSYS software, and the vibration modes and added mass were calculated by FEM. Further, the effect of different outer shell rigidity on the added mass of coaxial cylindrical shells was studied by changing the material parameters of the outer shell.","PeriodicalId":365848,"journal":{"name":"Volume 5: Nuclear Safety, Security, and Cyber Security","volume":"98 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"123023047","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

Study on the Plutonium Holdup Measurement in Glove-Box 手套箱中钚含率测量方法的研究

Volume 5: Nuclear Safety, Security, and Cyber Security Pub Date : 2022-08-08 DOI: 10.1115/icone29-90455

Yimei Cheng, Xiaoming Xu, Honghe Yin, Xinjun Li, Sijia Wang

引用次数: 0

Modal analysis and additional fluid mass of coaxial three-layer thin-wall member in annular flow gap 同轴三层薄壁构件环空流隙模态分析及附加流体质量

Volume 5: Nuclear Safety, Security, and Cyber Security Pub Date : 2022-08-08 DOI: 10.1115/icone29-92274

Chaofan Zhang, D. Lu, Yu Liu, Haotian Qiu

{"title":"Modal analysis and additional fluid mass of coaxial three-layer thin-wall member in annular flow gap","authors":"Chaofan Zhang, D. Lu, Yu Liu, Haotian Qiu","doi":"10.1115/icone29-92274","DOIUrl":"https://doi.org/10.1115/icone29-92274","url":null,"abstract":"\u0000 The sodium-cold pool-type fast reactor is the preferred reactor type for the fourth generation advanced reactor research. The reactor structure of a pool-type fast reactor has the characteristics of large size, thin wall, and relatively low stiffness. Therefore, the seismic design, analysis, and verification of the pool-type fast reactor are the key concerns of the fast reactor safety evaluation. In the fast reactor, many important reactor structures, such as the main pump support cylinder, are immersed in the ring basin of the reactor body. These devices are equipped with thermal shields and can therefore be regarded as coaxial housing systems with water gaps between the cylinders. Under the seismic condition, the fluid-structure coupling effect between the shell and the water gap will change the natural frequency of the shell itself, and the change of structural vibration characteristics is very important to study the seismic performance of the equipment structure in the fast reactor. However, the calculation method based on the dry/wet modal frequency ratio is not suitable for the calculation of additional mass under non-full water conditions. In this paper, based on ANSYS finite element analysis method, a coaxial three-layer shell model with fluid clearance is established to simulate the main pump supporting cylinder and other equipment, and the modes under different frequencies are studied. The additional mass of fluid clearance under different modes is calculated by the relationship between fluid pressure field and shell areal-displacement during vibration. The results are of reference value to the structural design and test of coaxial multi-layer shells such as the support cylinder of the main pump of the fast reactor.","PeriodicalId":365848,"journal":{"name":"Volume 5: Nuclear Safety, Security, and Cyber Security","volume":"10 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"134143303","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

Comparison of Numerical Analysis Methods of Coolant Environmental Fatigue Based on Strain Rate Control 基于应变速率控制的冷却剂环境疲劳数值分析方法比较

Volume 5: Nuclear Safety, Security, and Cyber Security Pub Date : 2022-08-08 DOI: 10.1115/icone29-93631

Xuejiao Shao, Hai Xie, Yixion Zhang, Furui Xiong, Xin-Jian Wang, K. Shi, Mingdao Yu, Xuan Huang

{"title":"Comparison of Numerical Analysis Methods of Coolant Environmental Fatigue Based on Strain Rate Control","authors":"Xuejiao Shao, Hai Xie, Yixion Zhang, Furui Xiong, Xin-Jian Wang, K. Shi, Mingdao Yu, Xuan Huang","doi":"10.1115/icone29-93631","DOIUrl":"https://doi.org/10.1115/icone29-93631","url":null,"abstract":"\u0000 In this paper, the transformed strain rate of environmental fatigue correction factor (Fen), which is used to consider the influence of PWR primary coolant environment on material fatigue, is studied. EPRI’s guideline and the AFCEN’s probationary phase rule (RPP) No.3 of Volume VI in RCC-M 2017 edition provide two different calculation methods of transformed strain rate separately. NUREG CR-6909 gives two versions of prediction models of Fen for Low alloy steel, nickel base alloy and austenitic stainless steel which are the three main materials of the primary circuit system.\u0000 In this paper, the model and transients of Sample 2 in EPRI’s guideline are selected for calculation and comparison, so as to verify whether the analysis method is reasonable. Firstly, the fatigue analysis in air is carried out, and then based on the combination, the detailed calculation of strain rate is carried out to calculate environmental fatigue results. The analysis results are compared with the results of guideline, and the valuesare close. Then, the main pipeline safety injection nozzle components with small fatigue margin in PWR are selected to carry out environmental fatigue analysis. In the analysis, different methods of calculating modified strain rates are used, and different prediction models in CR-6909 are used. The coefficient of Fen integrated in RPP3 isconsidered, and the effects of various calculation methods on the results are compared.\u0000 The results show that for austenitic stainless steel, the results of RCC-M RPP3 method are mostly less than those of EPRI guidelines. Compared with the prediction model of NUREG CR-6909 version 0, the prediction model version 1 greatly decreases the Fen results.","PeriodicalId":365848,"journal":{"name":"Volume 5: Nuclear Safety, Security, and Cyber Security","volume":"7 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"130030668","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

Effect of Surface Machining on Stress Corrosion Cracking Sensitivity of 304L and 316L Austenite Stainless Steel 表面加工对304L和316L奥氏体不锈钢应力腐蚀开裂敏感性的影响

Volume 5: Nuclear Safety, Security, and Cyber Security Pub Date : 2022-08-08 DOI: 10.1115/icone29-90466

Huanchun Wu, Xinming Meng, Yao Han, Yanwei Zhang, Q. Peng

引用次数: 0

Numerical Study of the Effect of Different Tank Shapes on Liquid Sloshing Characteristics 不同槽形对液体晃动特性影响的数值研究

Volume 5: Nuclear Safety, Security, and Cyber Security Pub Date : 2022-08-08 DOI: 10.1115/icone29-92150

Yuxuan Zhu, D. Lu, Dong Li, Yu Liu

{"title":"Numerical Study of the Effect of Different Tank Shapes on Liquid Sloshing Characteristics","authors":"Yuxuan Zhu, D. Lu, Dong Li, Yu Liu","doi":"10.1115/icone29-92150","DOIUrl":"https://doi.org/10.1115/icone29-92150","url":null,"abstract":"\u0000 In nuclear power engineering, there are many tanks with irregular shapes (e.g., the cooling water tank of the containment, etc.), whose shapes are quite different from the traditional rectangular tanks. Under seismic excitation, the sloshing of the liquid in the tank produces the fluid-structure interaction (FSI) with the structure. It is crucial to study the sloshing characteristics of the water tank during the design of the reactor structure. There is a difference between the sloshing characteristics of irregularly shaped tanks and rectangular tanks, but there are few studies on this difference and the significance of the difference needs to be further investigated. To explore the aforementioned issues, based on the fluid-structure interaction theory and Housner’s equivalent mechanical model, the finite element models of the irregularly shaped water tank and the regular water tank (rectangular) are established by ANSYS software. The effect of the tank shape on the sloshing frequency and added mass of water in the tank is studied by modal analysis and calculation of the added mass. Further, the significance of the effect of tank shape on the natural and dynamic characteristics of tanks is investigated by comparing the variability of the sloshing frequency and the added mass. The results can guide the fluid-structure interaction problem in nuclear power engineering and provide a reference for the structural design of similar irregular water tanks, thus improving the safety and economy of reactor design.","PeriodicalId":365848,"journal":{"name":"Volume 5: Nuclear Safety, Security, and Cyber Security","volume":"96 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"121958898","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

Experimental Studies and Mechanical Properties Analysis of Three-Dimensional Oblique Rotating Friction Seismic Isolators 三维斜转摩擦隔震器的试验研究及力学性能分析

Volume 5: Nuclear Safety, Security, and Cyber Security Pub Date : 2022-08-08 DOI: 10.1115/icone29-92541

S. Wu, Wenguang Liu, W. He

{"title":"Experimental Studies and Mechanical Properties Analysis of Three-Dimensional Oblique Rotating Friction Seismic Isolators","authors":"S. Wu, Wenguang Liu, W. He","doi":"10.1115/icone29-92541","DOIUrl":"https://doi.org/10.1115/icone29-92541","url":null,"abstract":"\u0000 Traditional isolation devices widely provide protection only against the horizontal components of earthquake motions. The vertical ground motions are transmitted through the isolation system unchanged or even magnified. Thus, in this paper, a mechanical model of a novel three-dimensional oblique rotating friction seismic isolator is proposed. The device with oblique-torsion coupling deformation is designed by combining three inclined rubber bearings. The test results show that the device have asymmetric behavior and a plump hysteretic loop in a vertical direction. After three times cyclic loading, the slope of the curve for the device hardly changes, and there is no damage in the loading process. The error of vertical post-yield stiffness of the device between the experimental result and theoretical prediction is within 10%, and it is in good agreement with the theoretical model prediction. In addition, the effects of different parameters are highlighted based on the theoretical mechanical model. The results show that the inclination angle, the friction coefficient, radius of PTFE, distance from the center of the inclined LRB to the center of the rotating block, and the performance of the inclined LRBs strongly influence the vertical behavior of the proposed device and should be worthy of attention in the design of devices.","PeriodicalId":365848,"journal":{"name":"Volume 5: Nuclear Safety, Security, and Cyber Security","volume":"21 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"127163797","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