Abstract
The guillotine rupture of 4 tubes is assumed as a design basis regarding the large-leak sodium-water reaction in the system of the MONJU steam generator. Three kinds of analyses were performed with the view to showing the integrity of the steam generator system on the reaction. The first one is the analysis of the initial pressure spike, assuming the initial guillotine rupture of 1 tube. The analysis was performed by utilizing one-dimensional sphere-cylinder model code SWAC-7 and two-dimensional axisymmetric code PISCES 2DL. The second one is the analysis of the secondary peak pressure and its propagation in the system, assuming the instantaneous guillotine rupture of 4 tubes. The third one is the analysis of the dynamic deformation of the steam generator shell. The integrity of the steam generator system was shown by the analyses. (author)
Citation Formats
Sakano, K, Shindo, Y, and Hori, M.
Large-leak sodium-water reaction analysis for steam generators.
IAEA: N. p.,
1975.
Web.
Sakano, K, Shindo, Y, & Hori, M.
Large-leak sodium-water reaction analysis for steam generators.
IAEA.
Sakano, K, Shindo, Y, and Hori, M.
1975.
"Large-leak sodium-water reaction analysis for steam generators."
IAEA.
@misc{etde_20107675,
title = {Large-leak sodium-water reaction analysis for steam generators}
author = {Sakano, K, Shindo, Y, and Hori, M}
abstractNote = {The guillotine rupture of 4 tubes is assumed as a design basis regarding the large-leak sodium-water reaction in the system of the MONJU steam generator. Three kinds of analyses were performed with the view to showing the integrity of the steam generator system on the reaction. The first one is the analysis of the initial pressure spike, assuming the initial guillotine rupture of 1 tube. The analysis was performed by utilizing one-dimensional sphere-cylinder model code SWAC-7 and two-dimensional axisymmetric code PISCES 2DL. The second one is the analysis of the secondary peak pressure and its propagation in the system, assuming the instantaneous guillotine rupture of 4 tubes. The third one is the analysis of the dynamic deformation of the steam generator shell. The integrity of the steam generator system was shown by the analyses. (author)}
place = {IAEA}
year = {1975}
month = {Jul}
}
title = {Large-leak sodium-water reaction analysis for steam generators}
author = {Sakano, K, Shindo, Y, and Hori, M}
abstractNote = {The guillotine rupture of 4 tubes is assumed as a design basis regarding the large-leak sodium-water reaction in the system of the MONJU steam generator. Three kinds of analyses were performed with the view to showing the integrity of the steam generator system on the reaction. The first one is the analysis of the initial pressure spike, assuming the initial guillotine rupture of 1 tube. The analysis was performed by utilizing one-dimensional sphere-cylinder model code SWAC-7 and two-dimensional axisymmetric code PISCES 2DL. The second one is the analysis of the secondary peak pressure and its propagation in the system, assuming the instantaneous guillotine rupture of 4 tubes. The third one is the analysis of the dynamic deformation of the steam generator shell. The integrity of the steam generator system was shown by the analyses. (author)}
place = {IAEA}
year = {1975}
month = {Jul}
}