Arid
DOI10.2172/5402932
报告编号WSRC-TR-91-0557
来源IDOSTI_ID: 5402932
Summary report on four foot septifoil cooling experiment
Randolph, H.W.; Collins, S.L.; Verebelyi, D.T.; Foti, D.J.
英文摘要Cooling parameters for some of the SRS reactor internal components are computed using the Transient Reactor Analysis Code, TRAC.'' In order to benchmark the code, the Safety Analysis Group of SRL requested an experiment to provide measurements of cooling parameters in a well defined physical system utilizing SRS reactor component(s). The experiment selected included a short length of septifoil with both top and bottom fittings containing five simulated control rods in an unseated'' configuration. Power level to be supplied to the rods was targeted at 2.5 kilowatts per foot. The septifoil segment was to be operated with no forced flow in order to evaluate thermal-hydraulic cooling. Parameters to be measured for comparison with code predictions were basic cooling phenomena, incidence of film boiling, thermal-hydraulic flow rate, pressure rise, and ratio of heat transfer through the wall of the assembly vs heat transfer to axial water flow through the assembly. Experimental apparatus was designed and assembled incorporating five simulated control rods four feet long, joule heated inside a five foot length of type Q'' septifoil. Water at 70 C was fed independently to the bottom inlet and along the outside of the septifoil. Water flowing along the outside of the septifoil was in confined flow and provided calorimetry to measure power flow through the septifoil housing. A shadowgraph technique was developed and used to monitor unforced flow of water pumped thermal-hydraulically through the septifoil. Electrical power of 10,000 to 70,000 watts was fed to the simulated rods from a dc power supply. Computer data acquisition was accomplished using LabView'' software programmed to match the configuration of the experiment along with scanning digital voltmeters and requisite signal sensors. Video camcorders were used to provide video records of six areas of the experiment.
出版年1991
报告类型Technical Report
语种英语
国家美国
来源学科分类22 GENERAL STUDIES OF NUCLEAR REACTORS ; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS ; CONTROL ELEMENTS ; HEAT TRANSFER ; T CODES ; SPECIAL PRODUCTION REACTORS ; BENCHMARKS ; DATA ACQUISITION SYSTEMS ; FILM BOILING ; FLOW RATE ; FOILS ; HYDRAULICS ; REACTOR COOLING SYSTEMS ; REACTOR SAFETY ; TESTING ; BOILING ; COMPUTER CODES ; COOLING SYSTEMS ; ENERGY TRANSFER ; FLUID MECHANICS ; MECHANICS ; PHASE TRANSFORMATIONS ; PRODUCTION REACTORS ; REACTOR COMPONENTS ; REACTORS ; SAFETY 220900* -- Nuclear Reactor Technology-- Reactor Safety ; 220600 -- Nuclear Reactor Technology-- Research, Test & Experimental Reactors
URLhttp://www.osti.gov/scitech/servlets/purl/5402932
资源类型科技报告
条目标识符http://119.78.100.177/qdio/handle/2XILL650/264557
推荐引用方式
GB/T 7714
Randolph, H.W.,Collins, S.L.,Verebelyi, D.T.,et al. Summary report on four foot septifoil cooling experiment,1991.
条目包含的文件
条目无相关文件。
个性服务
推荐该条目
保存到收藏夹
导出为Endnote文件
谷歌学术
谷歌学术中相似的文章
[Randolph, H.W.]的文章
[Collins, S.L.]的文章
[Verebelyi, D.T.]的文章
百度学术
百度学术中相似的文章
[Randolph, H.W.]的文章
[Collins, S.L.]的文章
[Verebelyi, D.T.]的文章
必应学术
必应学术中相似的文章
[Randolph, H.W.]的文章
[Collins, S.L.]的文章
[Verebelyi, D.T.]的文章
相关权益政策
暂无数据
收藏/分享

除非特别说明,本系统中所有内容都受版权保护,并保留所有权利。