Investigation on spent fuel characteristics of reduced-moderation water reactor (RMWR)

• Published in: Nuclear engineering and design Vol. 238; no. 7; pp. 1601 - 1611
• Main Authors: Fukaya, Y., Okubo, T., Uchikawa, S.
• Format: Journal Article
• Language: English
• Published: Amsterdam Elsevier B.V 01-07-2008; Elsevier
• Subjects: Applied sciences; Controled nuclear fusion plants; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Fission nuclear power plants; Fuels; Installations for energy generation and conversion: thermal and electrical energy; Nuclear fuels; Preparation and processing of nuclear fuels; Cross section (collision); Waste disposal; Modeling; Molybdenum; Light water reactor; Nuclear reactor; Actinide; Boiling water reactor; Fission product; Platinum; Fast breeder; Mixed fuel; Plutonium; Recycling; Reactor core; Irradiated nuclear fuel; Radioactivity; Pressurized water reactor
• ISSN: 0029-5493; 1872-759X
• DOI: 10.1016/j.nucengdes.2007.10.014

The spent fuel characteristics of the reduced-moderation water reactor (RMWR) have been investigated using the SWAT and ORIGEN codes. RMWR is an advanced LWR concept for plutonium recycling by using the MOX fuel. In the code calculation, the ORIGEN libraries such as one-group cross-section data prepared for RMWR were necessary. Since there were no open libraries for RMWR, they were produced in this study by using the SWAT code. New libraries based on the heterogeneous core modeling in the axial direction and with the variable actinide cross-section (VXSEC) option were produced and selected as the representative ORIGEN libraries for RMWR. 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, such as PWR, BWR, high burn-up PWR, full-MOX-PWR, full-MOX-BWR and FBR, were also evaluated with ORIGEN.
It has been found that about a half of the decay heat of the RMWR spent fuel comes from the actinides nuclides. It is the same with the radioactivity. 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. The decay heat and the radioactivity from the fission products (FPs) in the spent fuel mainly depend on the burn-up and the burn-up time rather than the reactor type. Therefore, the decay heat and the radioactivity from FPs in the RMWR spent fuel are smaller, reflecting its relatively long burn-up time resulted from its core characteristics with the high conversion ratio. The radioactivity from the actinides in the spent fuel mainly depends on the
241Pu content in the initial fuel, and the decay heat mainly depends on
238Pu and
244Cm. The contribution of
244Cm is much smaller in RMWR than in MOX-LWRs because of the difference in the spectrum. 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.