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JAEA Reports

Safety analysis of JMTR LEU fuel cores, 2; Thermohydraulic analysis

Ishitsuka, Etsuo; Sato, Takeshi; ; ; Saito, Minoru;

JAERI-M 92-096, 95 Pages, 1992/07

JAERI-M-92-096.pdf:2.5MB

no abstracts in English

JAEA Reports

Design Basis of Thermo by Drodynamics for JRR-3

Sudo, Yukio; ; ; *;

JAERI-M 84-079, 141 Pages, 1984/05

JAERI-M-84-079.pdf:2.97MB

no abstracts in English

JAEA Reports

Development of Heat Transfer Package for JRR-3 Thermofydrodynamic Analysis

Sudo, Yukio; ; Hirano, Masashi;

JAERI-M 84-066, 74 Pages, 1984/03

JAERI-M-84-066.pdf:1.72MB

no abstracts in English

Oral presentation

Safety evaluation of decay heat removal characteristics in a pool-type sodium-cooled fast reactor

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.

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