2023 Annual Meeting

Presentation information

Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 501-1 Basic Properties

[2F05-07] Machine Learning, Fast Reactor Recycling, Effective Utilization of FP

Tue. Mar 14, 2023 11:05 AM - 11:55 AM Room F (12 Bildg.3F 1232)

Chair:Masashi WATANABE(JAEA)

11:20 AM - 11:35 AM

[2F06] Demonstration research on fast reactor recycling using low decontaminated MA-bearing MOX fuels

(9)Microstructure and thermal conductivity of MOX with simulated FPs

*Yuta Horii1, Shun Hirooka1, Hiroki Uno2, Masahiro Ogasawara2, Tetsuya Tamura2, Tadahisa Yamada2, Naoya Furusawa2, Shinya Nakamichi1, Tatsutoshi Murakami1, Masato Kato1 (1. JAEA, 2. Inspection Development)

Keywords:MOX, thermal conductivity, simulated FPs, homogeneity, low-decontaminated fuel

The low-decontaminated fuel which contains significant amount of fission products (FPs) has been investigated as a fuel for the advanced fast reactor cycle. In this cycle, it is expected to reduce reprocessing cost and strengthen nuclear proliferation resistance of recovered plutonium accompanying high radiation dose FPs. As part of studies on physical properties of low-decontaminated fuel pellets, Nd2O3/Sm2O3 powders were added to the MOX raw powder as simulated fission products (FPs). The effects of simulated FPs on thermal conductivity were evaluated focusing on the microstructural homogeneities of simulated FPs. From the results of thermal diffusivity measurement and the EPMA mapping, the homogeneous simulated FPs decreased the thermal conductivity of the MOX.