Kerntechnik最新文献_第10页

Updating risk model for SGTR accident based on success criteria analysis 基于成功准则分析的SGTR事故风险模型更新

IF 0.5 4区工程技术

Kerntechnik Pub Date : 2022-06-24 DOI: 10.1515/kern-2022-0007

M. Mohammadnia, S. M. Hoseyni, Kaveh Karimi

引用次数: 0

The investigation of heat transfer enhancement by using different mixture conditions of graphene nanofluids on a downward facing surface 不同混合条件下石墨烯纳米流体对下表面强化传热的研究

IF 0.5 4区工程技术

Kerntechnik Pub Date : 2022-06-16 DOI: 10.1515/kern-2022-0028

Shiqi Wang, H. Hsieh, Zhibo Zhang, Yuan Gao, Zhe Zhou, Jia Gao

引用次数: 2

Numerical determination of condensation pressure drop of various refrigerants in smooth and micro-fin tubes via ANN method 用人工神经网络方法计算各种制冷剂在光滑和微翅片管内的冷凝压降

IF 0.5 4区工程技术

Kerntechnik Pub Date : 2022-06-15 DOI: 10.1515/kern-2022-0037

A. B. Çolak, A. Celen, A. S. Dalkılıç

引用次数: 1

The analysis of fire ignition frequency calculation for small modular light water reactors 小型模块化轻水堆着火频率计算分析

IF 0.5 4区工程技术

Kerntechnik Pub Date : 2022-06-13 DOI: 10.1515/kern-2022-0030

Hongxia Jiang, Zihan Liu, C. Peng

{"title":"The analysis of fire ignition frequency calculation for small modular light water reactors","authors":"Hongxia Jiang, Zihan Liu, C. Peng","doi":"10.1515/kern-2022-0030","DOIUrl":"https://doi.org/10.1515/kern-2022-0030","url":null,"abstract":"Abstract With the release of reports such as NUREG/CR-6850, the calculation of ignition frequency concerning general large-scale Pressurized Water Reactors (PWRs) has matured. However, there is currently a lack of methods for calculating the ignition frequency in the case of Small Modular Light Water Reactors (SMRs). By studying the calculation of ignition frequency reported in NUREG/CR-6850, we propose a method for calculating the ignition frequency in SMRs, which is based on the generic ignition frequency at the component level. The problem of counting ignition sources is discussed in detail, and we determine the component-level ignition frequencies due to different types of ignition sources. In order to improve the calculation of the ignition frequency in SMRs, this paper provides two methods, which are based on the prior lognormal distribution and the prior Gamma distribution, respectively, for updating ignition frequency. We also consider the effect of the accumulation of fire events on the posterior mean determined by both methods. In this paper, we suggest that the method based on the prior lognormal distribution should be used in the initial stage of updates of ignition frequency. As data for plant-specific events accumulate, the approach based on the prior Gamma distribution should be considered.","PeriodicalId":17787,"journal":{"name":"Kerntechnik","volume":"23 1","pages":"409 - 419"},"PeriodicalIF":0.5,"publicationDate":"2022-06-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85274100","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Computational study of subcooled water injection into steam line: effect of Reynolds number on flow transition to study condensation induced water hammers 蒸汽管道注入过冷水的计算研究:雷诺数对流动过渡的影响研究冷凝水锤

IF 0.5 4区工程技术

Kerntechnik Pub Date : 2022-06-03 DOI: 10.1515/kern-2021-1061

A. Quddus, Ajmal Shah, K. Qureshi, M. K. Ayub, M. Iqbal, A. Samee

{"title":"Computational study of subcooled water injection into steam line: effect of Reynolds number on flow transition to study condensation induced water hammers","authors":"A. Quddus, Ajmal Shah, K. Qureshi, M. K. Ayub, M. Iqbal, A. Samee","doi":"10.1515/kern-2021-1061","DOIUrl":"https://doi.org/10.1515/kern-2021-1061","url":null,"abstract":"Abstract The direct contact condensation (DCC) of steam in subcooled water encounters in wide range of the industrial applications. On one side, it is an efficient and rapid, mass and heat transfer phenomenon. But, on the other side, it may generate condensation induced water hammers (CIWH) events which may cause high pressure peaks resulting in severe damage to the mechanical systems. This computational study intends to explore the underlying physics of CIWH events while injecting subcooled water into steam filled horizontal pipe section. The Reynolds number is varied from, Re w = 60,750 to 646,900, to study the flow regimes (stratified and slug), onset of CIWH and local flooding conditions. The results have been compared with the published data and found in good agreement. It has been observed that for Re w = 182,300, flow remains stratified. However, the flow regime changes from stratified to slug flow at Re w = 303,850–646,900, possibly due to the onset of CIWH. Extensive steam pockets have been observed at Re w = 303,850, which may be considered as onset of CIWH. Local flooding condition is also started at Re w = 303,850 and is observed to be shifted upstream with the increase in Reynolds number. This study is considered to be useful for the safe design and economical operation of the relevant systems in nuclear and other related industry.","PeriodicalId":17787,"journal":{"name":"Kerntechnik","volume":"126 1","pages":"470 - 483"},"PeriodicalIF":0.5,"publicationDate":"2022-06-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87855019","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 3

Experimental investigation of thermal characteristics of a cylindrical heat pipe under varied system parameters and operating conditions 不同系统参数和工况下圆柱形热管热特性的实验研究

IF 0.5 4区工程技术

Kerntechnik Pub Date : 2022-06-03 DOI: 10.1515/kern-2022-0008

Nidhi Nigam, A. Patil, M. Kumar

引用次数: 0

Steady state thermal hydraulic modelling of WWR-S tank-in-pool research reactor for the purpose of its power upgrading 基于WWR-S型池中储罐研究堆功率升级的稳态热水力建模

IF 0.5 4区工程技术

Kerntechnik Pub Date : 2022-05-26 DOI: 10.1515/kern-2022-0003

S. Ibrahim, M. Esawy, Hossam I. Yousif

{"title":"Steady state thermal hydraulic modelling of WWR-S tank-in-pool research reactor for the purpose of its power upgrading","authors":"S. Ibrahim, M. Esawy, Hossam I. Yousif","doi":"10.1515/kern-2022-0003","DOIUrl":"https://doi.org/10.1515/kern-2022-0003","url":null,"abstract":"Abstract This paper presents a newly developed steady state core thermal hydraulic model (named SSTH-RR10 model) for upgrading the Egyptian first Research Reactor (ETRR-1), from its original power of 2 MWth to a higher level of 10 MWth, by considering different types of nuclear fuels. The SSTH-RR10 model is capable to predict and calculate, by means of a developed computer program, all the steady state thermal hydraulic parameters for the defined core configuration for each fuel type at 10 MWth. Three different fuel types were investigated: the reference fuel EK-10 rod type, the MTR plate type, and the IRT-4M ducted type. For each fuel type, the distribution of central fuel, clad, and coolant temperatures for average and hot channels of the core were predicted in the axial direction. Power distributions and pressure gradients were predicted as well. Moreover, the program calculates the safety limits and margins against the critical phenomena encountered such as the Onset of Nucleate Boiling (ONB), Departure from Nucleate Boiling (DNB), and the Onset of Flow Instability (OFI). Results of the SSTH-RR10 program for benchmarks of powers of 2 and 10 MWth are verified by comparing it with the published results of the International Atomic Energy Agency (IAEA), and those published for other programs such as PARET code, and very good agreement is found. The safety margins against ONB and DNB were evaluated in which the minimum DNB ratio was found to be about 3.1, which gives a sufficient margin against the DNB. The present work gives confidence in the model results and applications.","PeriodicalId":17787,"journal":{"name":"Kerntechnik","volume":"81 1","pages":"452 - 469"},"PeriodicalIF":0.5,"publicationDate":"2022-05-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74243174","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Research on the application of 22Na radiolocation detection technology in advanced manufacturing process control 22Na射频定位检测技术在先进制造过程控制中的应用研究

IF 0.5 4区工程技术

Kerntechnik Pub Date : 2022-05-17 DOI: 10.1515/kern-2021-1031

Siming Guo, Jun Zhang, Lei Shi, Qingwen Chen, Wang Chen

引用次数: 1

Improving FNMC for the matrix effect of spherical shell plutonium samples 改进球壳钚样品基体效应的FNMC

IF 0.5 4区工程技术

Kerntechnik Pub Date : 2022-05-17 DOI: 10.1515/kern-2021-0019

S. Hou, Ji-jun Luo

引用次数: 0

Frictional wear characteristics of nickel-based alloy and reactor material in pressure vessel reactor 压力容器反应器中镍基合金与反应器材料的摩擦磨损特性

IF 0.5 4区工程技术

Kerntechnik Pub Date : 2022-05-12 DOI: 10.1515/kern-2021-1026

Wei Zhang, Hanbo Lin, Jun Tao, Chunhua Bian, Ming-An Hu, F. Xu, Linjun Xie

{"title":"Frictional wear characteristics of nickel-based alloy and reactor material in pressure vessel reactor","authors":"Wei Zhang, Hanbo Lin, Jun Tao, Chunhua Bian, Ming-An Hu, F. Xu, Linjun Xie","doi":"10.1515/kern-2021-1026","DOIUrl":"https://doi.org/10.1515/kern-2021-1026","url":null,"abstract":"Abstract The reactor pressure vessel was contact sealed with a double-channel O-ring made of Inconel 718 alloy and nuclear power material SA508. The fretting wear characteristics of Inconel 718 O-tube and SA508 plate friction pair were tested by fretting wear testing machine to explore the failure mechanism of reactor pressure vessel seal system. The test conditions are as follows: normal temperature, normal loads of 10, 20, and 40 N, displacement amplitude of 600 μm, the number of cycles of 10,000, and frequency of 4 Hz. Results show that the coefficient of friction (COF) increased with increasing normal force. Significant material losses were detected during the relative sliding of the contact surface of SA508. A large number of abrasive dust accumulated at the edge of the contact zone, forming a large number of oxides. During the friction of Inconel 718 O-ring, plastic deformation occurred, and a plastic flow layer was formed. The plastic deformation flow at the contact point formed an adhesive connection point, producing adhesive wear and oxidative wear. The wear mechanism was characterized by the combination of oxidative wear and abrasive wear.","PeriodicalId":17787,"journal":{"name":"Kerntechnik","volume":"12 1","pages":"278 - 286"},"PeriodicalIF":0.5,"publicationDate":"2022-05-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79961441","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 1