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Large-leak sodium–water reaction accident analysis of sodium-cooled fast reactor.
- Source :
-
Progress in Nuclear Energy . Dec2021, Vol. 142, pN.PAG-N.PAG. 1p. - Publication Year :
- 2021
-
Abstract
- A sodium-cooled fast reactor (SFR) is one of Generation IV nuclear systems. The once-through steam generator is important for heat transfer and acts as a barrier to separate the sodium and water. If the heat transfer tube breaks, a sodium–water reaction (SWR) occurs, and the integrity of the secondary loop may be destroyed. Thus, a dynamic model to analyze the SWR must be developed, especially for a large-leak SWR. A large-leak SWR analysis model was developed for an SFR, consisting of four modules: water/steam leakage rate, hydrogen bubble growth, pressure wave propagation, and SWR protection system action. A large-leak SWR accident was simulated using this model, and the process was investigated. Sensitivity analysis was performed for the critical parameters, and the parameters with a key influence on the large-leak SWR were determined. The results are significant for the design of the steam generator and the SWR protection system. • A large-leak SWR analysis method was developed. • The large-leak SWR of the SFR was simulated and analyzed. • Sensitivity analysis was performed to investigate the critical parameters on SWR. • The results are of significance to design of steam generator of the SFR. [ABSTRACT FROM AUTHOR]
Details
- Language :
- English
- ISSN :
- 01491970
- Volume :
- 142
- Database :
- Academic Search Index
- Journal :
- Progress in Nuclear Energy
- Publication Type :
- Academic Journal
- Accession number :
- 153960657
- Full Text :
- https://doi.org/10.1016/j.pnucene.2021.104010