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Large-leak sodium-water reaction analysis for steam generators

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)
Publication Date:
Jul 01, 1975
Product Type:
Conference
Report Number:
IWGFR-1
Reference Number:
EDB-00:099557
Resource Relation:
Conference: Study group meeting on steam generators for LMFBR's, Bensberg (Germany), 14-17 Oct 1974; Other Information: 8 refs, 10 figs, 2 tabs; PBD: Jul 1975; Related Information: In: Study group meeting on steam generators for LMFBR's. Summary report, 334 pages.
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CALCULATION METHODS; DESIGN BASIS ACCIDENTS; MOLTEN METAL-WATER REACTIONS; MONJU REACTOR; PRESSURE DEPENDENCE; RUPTURES; SODIUM; STEAM GENERATORS; TUBES
OSTI ID:
20107675
Research Organizations:
International Atomic Energy Agency, International Working Group on Fast Reactors, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
TRN: XA0055695054512
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
page(s) 104-109
Announcement Date:

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}
}