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Mascari, F.*; 中村 秀夫; De Rosa, F.*; D'Auria, F.*
no journal, ,
In the development and safety evaluation of LWRs, thermal hydraulic analysis of the reactor, containment and their coupling is essential to understand the accident phenomena. To reproduce the behavior in a scaled model, it is necessary to properly characterize thermal hydraulics both in the local and integral responses. The facility geometry and test conditions should then be correctly derived according to scaling laws to avoid scaling distortions that could compromise the target phenomena identified by PIRT process. Many scaling approach and methods have thus been developed. Together with the scaling analysis, computer codes may be used in supporting the design of test facilities, assessing the scale distortions, and verifying the selected scaling method. However, since the closure laws in the computer code are mainly based on scaled test data, the extrapolation of code results remains a challenging and open issue. This paper provides some insights about the methods used in the scaling.
中村 秀夫
no journal, ,
軽水炉の安全評価に用いるシステム解析コードの性能評価(V&V)を行う時、対象とする軽水炉の熱水力現象に関するスケーリングの考慮が必要となる。ここでは、V&Vパネルセッションへの話題として、日本原子力学会標準「シミュレーションの信頼性確保に関するガイドライン:2015」とOECD/NEAによるScalingに関するState-of-Art Reportの比較から、システム解析コードの備えるべき性能と課題について共通するポイントを、原子力機構が実施してきたOECD/NEA ROSAプロジェクトの例などを引き合いにして指摘し、かつ、軽水炉事故時の現象評価における問題点とCFD解析の役割と課題などを合わせて指摘した。