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• 資料種別: 文書・図像類
• タイトル: None
• 著者・編者: 望月 弘保; 速水 義孝
• 著者標目: 望月 弘保; 速水 義孝
• 出版年月日等: 1988-02
• 出版年（W3CDTF）: 1988-02
• 並列タイトル等: Development of Transient Analysis Code for Primary Cooling System Couoled with Reactor Auxiliary Systems
• タイトル（掲載誌）: PNC TN9410 88-015
• 本文の言語コード: eng
• 対象利用者: 一般
• 一般注記: A plant transient analysis code has been developed to analyze the thermal hydraulics in the primary cooling system, coupled with dynamic characteristics of the residual heat removal (RHR) system and the reactor core isolation cooling (RCIC) system. A new numerical scheme named "flow distribution function" has been developed to calculate long term transients quickly. Prediction accuracies of the code for each function of components, such as thermal transient of a heat exchanger, thermal transport in a pipes, and flow control characteristic of a control system were examined by the experimental data obtained from the tests using the full mock-ups of the advanced thermal reactor (ATR) and the prototype reactor "Fugen". Prediction accuracy for the whole plant behavior was verified by the test simulating the loss-of-power-transient with succeeding RCIC injection at the "Fugen". Main parameters of the plant are predicted within $\pm$10\% error. The CPU time needed for the calculation is about 1/30 - 1/300 of the physical time when a super computer VP-100 is used.; None
• 一次資料へのリンクURL: /PNC-TN9410-88-015.pdf （fulltext）; https://jopss.jaea.go.jp/pdfdata/PNC-TN9410-88-015.pdf
• オンライン閲覧公開範囲: 限定公開
• 連携機関・データベース: 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
• 提供元機関・データベース: 日本原子力研究開発機構 : JOPSS:JAEA Originated Papers Searching System

• 要約等: A plant transient analysis code has been developed to analyze the thermal hydraulics in the primary cooling system, coupled with dynamic characteristi...