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The SA analysis codes can estimate the release of fission products (FPs) into environment and distribution of FPs in a reactor based on the models of thermal-hydraulics and FP behaviors at each region in a reactor, from reactor pressure vessel (RPV) to containment vessel (CV) and reactor building (RB) through reactor cooling system (RCS). Thus, the improvement of FP models is one of the key issues for the improved source term (IAEA, 2008). The FP models have been improved based on results of the researches on various FP behaviors (Soffer, 1995; Clément, 2007; Allelein, 2009). The main issues for the improvement are FP chemistry (Haste, 2009; Miwa 2015) and treatment of fine space resolution in a reactor. As for the latter issue of fine space resolution, it is especially important for the decommissioning of 1F since a detailed and fine FP distribution is required (Nuclear Damage Compensation and Decommissioning Facilitation

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