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• Material Type: 文書・図像類
• Title: None
• Author/Editor: 姫野 嘉昭; 宮原 信哉; 森井 正; 佐々木 和一
• Author Heading: 姫野 嘉昭; 宮原 信哉; 森井 正; 佐々木 和一
• Publication Date: 1988-10
• Publication Date (W3CDTF): 1988-10
• Alternative Title: Engineering Scale Test on Sodium Leak and Fire Accident and Its Consequences in Auxiliary Building of Fast Breeder Reactors
• Periodical title: PNC TN9410 88-145
• Text Language Code: eng
• Target Audience: 一般
• Note (General): Using sodium from 180kg to 3 metric tons, a series of tests has been conducted to develop the fire mitigation system and to study a design basis sodium leak accident and its consequences in the auxiliary building of the fast breeder reactor. In the test, flow pattern of a realistic leak from the sodium piping was investigated at first. Combustions of sodium in an open pool and a pool with a reduced opening were also studied together with combustion and flow of a sodium on an inclined steel liner and in a drain piping. Transient thermal conduction of a steel lined floor concrete during a sodium leak was tested and evaluated. In next, based on the results obtained, a fire mitigation system was developed and was mounted in a two storied concrete test rig. Then, a large scale test starting from a leak and ending by a self-extinguishment of a fire in the smothering tank was carried out. In final, consequences of sodium aerosols deposition on the reactor components and the electrical instruments have been experimentally studied.; None
• Source: /PNC-TN9410-88-145.pdf （fulltext）; https://jopss.jaea.go.jp/pdfdata/PNC-TN9410-88-145.pdf
• Access Restrictions: 限定公開
• Data Provider (Database): 国立情報学研究所 : 学術機関リポジトリデータベース（IRDB）（機関リポジトリ）; https://irdb.nii.ac.jp
• Original Data Provider (Database): 日本原子力研究開発機構 : JOPSS:JAEA Originated Papers Searching System

• Summary, etc.: Using sodium from 180kg to 3 metric tons, a series of tests has been conducted to develop the fire mitigation system and to study a design basis sodiu...