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Somolova, M.*; Terada, Atsuhiko; Takegami, Hiroaki; Iwatsuki, Jin
JAEA-Technology 2008-003, 41 Pages, 2008/12
Japan Atomic Energy Agency has been conducting a conceptual design study of nuclear hydrogen demonstration plant, that is, a thermo-chemical IS process hydrogen plant coupled with the High temperature Engineering Test Reactor (HTTR-IS), which will be planed to produce a large amount of hydrogen up to 1000m/h. As part of the conceptual design work of the HTTR-IS system, preliminary analyses on small break of a hydrogen pipeline in the IS process hydrogen plant was carried out as a first step of the safety analyses. This report presents analytical results of hydrogen diffusion behaviors predicted with a CFD code, in which a diffusion model focused on the turbulent Schmidt number was incorporated. By modifying diffusion model, especially a constant accompanying the turbulent Schmidt number in the diffusion term, analytical results was made agreed well with the experimental results.
Terada, Atsuhiko; Somolova, M.*; Takegami, Hiroaki; Iwatsuki, Jin; Murakami, Tomoyuki; Hino, Ryutaro; Shiozawa, Shusaku
no journal, ,
As part of the conceptual design work of the HTTR-IS system, preliminary analyses on small break of a hydrogen pipeline in the IS process hydrogen plant was carried out as a first step of the safety analyses. This report presents analytical results of hydrogen diffusion behaviors predicted with a CFD code, in which a simple model modified the boundary conditions and commpressibility of the hydrogen gas and turbulent parameter as the turbulent Schmit numbers was incorporated. Moreover, we evaluate the dispersion about parameters; height of release point, wind velocity, amount of released gas, etc. These result is useful to safety analysis for fire and blast accidents.