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- W156504377 abstract "Recently, the liquid-metal reactor research team of the Korea Atomic Energy Research Institute (KAERI) designed a 600 MWe sodium-cooled, metallic fueled fast reactor meeting the goals of Generation-IV, such as economics and proliferation resistance. In this paper, the core design analysis and its performance are reported. The core is designed to have a conversion ratio slightly larger than unity with no blanket assemblies in order not to produce an excess amount of high grade plutonium and to have no need for external feeds of fissile materials. To mitigate the sodium void reactivity of the fuel-self-sufficient core with no blanket assemblies, several design changes from a reference core are tried; reduction of the active core height, annular type cores with central dummy assemblies, and the use of moderator (BeO or ZrH{sub 2}) rods. As a result of the analysis, it is found that of the considered designs the use of moderator rods for the softening of the core neutron spectrum is the best choice for reducing the sodium void worth with the smallest changes from the reference fuel and assembly designs. The core analysis shows that the sodium void reactivity is reduced by {approx}2$ in comparison with the reference core andmore » the core has a much more negative fuel temperature reactivity feedback in comparison with the reference core. (authors)« less" @default.
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- W156504377 date "2004-07-01" @default.
- W156504377 modified "2023-09-24" @default.
- W156504377 title "Neutronic Design of KALIMER-600 Core with Moderator Rods" @default.
- W156504377 hasPublicationYear "2004" @default.
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