Close

Data details

 　　 　

<
Back
Taxonomy tree DisplayHide Taxonomy tree
Number of page views : 221
TitleMelting behavior of reactor core during severe accident of BWR 1 - fracture behavior of stainless structure materials by molten metallic and oxidic corium
Alternative title沸騰水型軽水炉過酷事故における炉心溶融物の挙動 1 - メタル系,酸化物系溶融物によるステンレス鋼製構造物の破壊
AuthorSumita, Takehiro(Tokyo Inst. of Technology)
AuthorKobayashi, Yoshinao(Tokyo Inst. of Technology)
AuthorUeda, Shigeru(Tohoku Univ.)
AuthorNakagiri, Toshio(Japan Atomic Energy Agency)
Issued date2018-09-05
Languagejpn
Page1p.
Typeproceedings
File FormatPDF
Taxonomy5-1-3-2 Experimental modelling/analysis
Taxonomy2-2-5 Containment system
Taxonomy5-1-2 Fuel condition diagnostics
Taxonomy(Computer Assigned)5-1-3 Reactor processes modelling   2-2 Design   5-1 Accident phenomena and progression   
Subject/Session_nameSession: 502-1 Nuclear Materials, Degradation, Radiation Effects, and Related Technology
Information sourceGo to external webpageRelation URL
Meeting title2018 Fall Annual Meeting of Atomic Energy Society of Japan
Related content
URIhttps://f-archive.jaea.go.jp/dspace/handle/faa/161368
collect date(WARP)2018-10-31