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Sanguanmith, S.*; Muroya, Yusa*; Meesungnoen, J.*; Lin, M.; Katsumura, Yosuke*; Mirsaleh Kohan, L.*; Guzonas, D. A.*; Stuart, C. R.*; Jay-Gerin, J.-P.*
Proceedings of 5th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR-5) (CD-ROM), 13 Pages, 2011/03
A re-examination of our Monte-Carlo modeling of the high-temperature radiolysis of liquid water by low linear energy transfer (LET 0.3 keV/m) radiation was undertaken in an attempt to reconcile our computed g-values of the various radiolytic products with newly measured or recently re-assessed experimental data over the range from 25 up to 350C. Using a global-fit procedure, experimental data were found to be best reproduced when a discontinuity in the temperature dependence of certain physicochemical parameters was introduced at 100-150C. The presence of such a discontinuity was hypothesized to be associated with a change in the liquid structure of water around these temperatures. In addition to the physicochemical factors intervening in the radiolysis, the importance of the reaction of H atoms with water in contributing to the unexplained yield of H above 200C was also investigated.
Nakatsuka, Toru; Mori, Hideo*; Akiba, Miyuki*; Ezato, Koichiro; Yasuoka, Makoto*
Proceedings of 5th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR-5) (CD-ROM), 12 Pages, 2011/03
In the thermal-hydraulic area of Japanese Supercritical Water Cooled Reactor (JSCWR) project, the main objective is to provide high-precision heat transfer and hydraulics resistance correlations of supercritical water which are necessary for the conceptual design of the core and fuel. For this purpose, a database was constructed from literature survey and previous research results. The most suitable correlation applied for circular tubes was selected based on the database and the range of application and predictive accuracy were defined. A thermal-hydraulics analysis code has been developed based on large eddy simulation, which is selected for simulation of the heat transfer deterioration, to give detailed information of thermal-hydraulics phenomena in a fuel bundle.