Investigation on spent fuel characteristics of Reduced-Moderation Water Reactor (RMWR)

Fukaya, Yuji   ; Okubo, Tsutomu; Uchikawa, Sadao

The spent fuel characteristics of the reduced-moderation water reactor (RMWR) have been investigated using the SWAT and ORIGEN codes. In the code calculation, the ORIGEN libraries for RMWR were necessary. Since there were no open libraries for RMWR, they were produced in this study by using the SWAT code. In order to investigate the characteristics of the RMWR spent fuel, the decay heat, the radioactivity and the content of each nuclide were evaluated with ORIGEN using these libraries. In this study, the spent fuel characteristics of other types of reactors were also evaluated with ORIGEN. It has been found that the decay heat and the radioactivity of the RMWR spent fuel are lower than those of full-MOX-LWRs and FBR, and are the same level as those of the high burn-up PWR. In addition, from the waste disposal point of view, the characteristics of the heat generation FP elements, the platinum group metals, Mo and the long-lived FPs (LLFPs) were also investigated.