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Journal Articles

Thermal conductivity measurement of uranium-plutonium mixed oxide doped with Nd/Sm as simulated fission products

Horii, Yuta; Hirooka, Shun; Uno, Hiroki*; Ogasawara, Masahiro*; Tamura, Tetsuya*; Yamada, Tadahisa*; Furusawa, Naoya*; Murakami, Tatsutoshi; Kato, Masato

Journal of Nuclear Materials, 588, p.154799_1 - 154799_20, 2024/01

https://doi.org/10.1016/j.jnucmat.2023.154799
 Times Cited Count：1 Percentile：68.31(Materials Science, Multidisciplinary)

The thermal conductivities of near-stoichiometric (U,Pu,Am)O$$_{2}$$ doped with Nd$$_{2}$$O$$_{3}$$/Sm$$_{2}$$O$$_{3}$$, which is major fission product (FP) generated by a uranium-plutonium mixed oxides (MOX) fuel irradiation, as simulated fission products are evaluated at 1073-1673 K. The thermal conductivities are calculated from the thermal diffusivities that are measured using the laser flash method. To evaluate the thermal conductivity from a homogeneity viewpoint of Nd/Sm cations in MOX, the specimens with different homogeneity of Nd/Sm are prepared using two kinds of powder made by ball-mill and fusion methods. A homogeneous Nd/Sm distribution decreases the thermal conductivity of MOX with increasing Nd/Sm content, whereas heterogeneous Nd/Sm has no influence. The effect of Nd/Sm on the thermal conductivity is studied using the classical phonon transport model (A+BT)$$^{-1}$$. The dependences of the coefficients A and B on the Nd/Sm content (C$$_{Nd}$$ and C$$_{Sm}$$, respectively) are evaluated as: A(mK/W)=1.70 $$times$$ 10$$^{-2}$$ + 0.93C$$_{Nd}$$ + 1.20C$$_{Sm}$$, B(m/W)=2.39 $$times$$ 10$$^{-4}$$.

Oral presentation

Measurement of melting temperature on MOX containing Np

Hirooka, Shun; Nakamichi, Shinya; Kato, Masato; Sato, Daisuke*; Furusawa, Naoya*

no journal, , 

no abstracts in English

Oral presentation

Demonstration research on fast reactor recycling using low decontaminated MA-bearing MOX fuels, 9; Microstructure and thermal conductivity of MOX with simulated FPs

Horii, Yuta; Hirooka, Shun; Uno, Hiroki*; Ogasawara, Masahiro*; Tamura, Tetsuya*; Yamada, Tadahisa*; Furusawa, Naoya*; Nakamichi, Shinya; Murakami, Tatsutoshi; Kato, Masato

no journal, , 

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, Nd$$_{2}$$O$$_{3}$$/Sm$$_{2}$$O$$_{3}$$ 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.

Oral presentation

Thermal conductivity measurement of homogenenous/heterogeneous simulated FP-doped MOX

Horii, Yuta; Hirooka, Shun; Uno, Hiroki*; Ogasawara, Masahiro*; Yamada, Tadahisa*; Furusawa, Naoya*; Murakami, Tatsutoshi

no journal, , 

no abstracts in English

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