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Ishitsuka, Etsuo; Sato, Takeshi; ; ; Saito, Minoru;
JAERI-M 92-096, 95 Pages, 1992/07
no abstracts in English
Sudo, Yukio; ; ; *;
JAERI-M 84-079, 141 Pages, 1984/05
no abstracts in English
Sudo, Yukio; ; Hirano, Masashi;
JAERI-M 84-066, 74 Pages, 1984/03
no abstracts in English
Tokizaki, Minako*; Tani, Akihiro*; Ando, Masato*; Onoda, Yuichi
no journal, ,
Decay heat removal characteristics were evaluated for the Pool-Type Sodium-Cooled Fast Reactor (600 MWe class power) under the categories of Anticipated Operational Occurrences (AOO) and Design Basis Accidents (DBA), and it is expected that the integrity of the core fuel and coolant boundary can be ensured in light of the safety criteria. In addition, from the viewpoint of robustness confirmation of decay heat removal function, decay heat removal characteristics of immersion type DRACS during independent operation were evaluated, and the prospect of core cooling by natural circulation was obtained.