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タイトルDevelopment of an analysis code for pressure wave propagation 2
その他のタイトルNone
DOI
本文(外部サイト)http://jolissrch-inter.tokai-sc.jaea.go.jp/pdfdata/PNC-TN251-74-27.pdf
参考URLhttp://jolissrch-inter.tokai-sc.jaea.go.jp/search/servlet/search?4003301
著者(英)R.Kawab; H.Ogasa; S.Uchid; M.Naito
発行日1974-10
発行機関などJAEA
刊行物名PNC-TN251 74-27
開始ページ1
終了ページ51
刊行年月日1974-10
言語en
内容記述If the leakage accident occurs in the steam generator of the sodiumcooled fast breeder reactor plant, sodium-water reaction takes place, producing a large amount of heat and hydrogen gas. So the suitablevent system will be prepared to protect the steam generator from highpressure transient. Although this high pressure also propagates to all the devices of the secondary loop, the considerations have ever been given only to the steam generator. Besides the steam generator,there is another critical component. The intermediate heat exchanger which includes the pressure boundary between the radioactive primary sodium loop and the non-radioactive secondary loop. So it will be indispensable to evaluate the intensity of pressure loaded upon this pressure boundary. Hitachi research laboratory of hitachi,ltd. developed a digitalcomputing code to analyze the pressure wave propagation phenomena under contract with the power reactor and nuclear fuel development corporation. The typical features of the code are a
著者所属: 日本原子力研究開発機構(JAEA)
資料種別Technical Report
URIhttps://repository.exst.jaxa.jp/dspace/handle/a-is/619313


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