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Bae, Y. Y.; Hwang, Y. D.; Cho, B. H. and others
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)1999
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)1999
AbstractAbstract
[en] Basic design of SMART adopts the new advanced technologies which were not applied in the existing 1000MWe PWR. However, the R and D experience on these advanced essential technologies is lacking in domestic nuclear industry. Recently, a research on these advanced technologies has been performed as a part of the mid-and-long term nuclear R and D program, but the research was limited only for the small scale fundamental study. The research on these essential technologies such as helically coiled tube steam generator, self pressurizer, core cooling by natural circulation required for the development of integral reactor SMART have not been conducted in full scale. This project, therefore, was performed for the development of analysis models and methodologies, system analysis and thermal hydraulic experiments on the essential technologies to be applied to the 300MWe capacity of integral reactor SMART and the advanced passive reactor expected to be developed in near future with the emphasis on experimental investigation. (author)
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Mar 1999; 349 p; 70 refs, 62 figs, 22 tabs
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