Close

Data details

    
Number of page views : 15
TitleDevelopment of reactor building and containment vessel thermo-fluid dynamics code, Advance/BAROC 10 - improvements and sample analysis to simulate transient behavior of FP aerosol leak through the shield plug
Alternative title過酷事故時原子炉建屋・格納容器の熱流動解析コードAdvance/BAROCの開発 10 - 原子炉ウェル上部のシールドプラグからのFPエアロゾル漏洩の過渡変化を模擬するための機能追加と事例解析
AuthorTakahashi, Atsuo(AdvanceSoft Corp.)
AuthorMitsuhashi, Toshiharu(AdvanceSoft Corp.)
AuthorHamano, Achihiro(AdvanceSoft Corp.)
AuthorOnishi, Fumitomo(AdvanceSoft Corp.)
AuthorHadachi, Hirotaka(AdvanceSoft Corp.)
AuthorKoike, Hideaki(AdvanceSoft Corp.)
AuthorNaitoh, Masanori(AdvanceSoft Corp.)
Issued date2024-03-28
Languagejpn
Pagep.3D10
Typeproceedings
File FormatPDF
Taxonomy5-3 Waste management
Taxonomy5-1-3-3 Numerical modelling/analysis
Taxonomy2-2-5 Containment system
Taxonomy(Computer Assigned)5. Scientific and Technical Support   5-1-3 Reactor processes modelling   2-2 Design   
Subject/Session_nameNuclear Safety Engineering (Safety Design, Safety Assessment/Analysis, Management)
Information sourceGo to literature copy applicationRelation URL
Meeting title2024 Annual Meeting of Atomic Energy Society of Japan
Related content
Related sites
時間軸情報:燃料デブリ取り出し
時間軸情報:PCV/RPV/建屋の解体
時間軸情報:汚染水対策
時間軸情報:処理・処分・環境回復
URIhttps://f-archive.jaea.go.jp/dspace/handle/faa/295220
collect date(WARP)2024-07-25