Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
7965339 | Journal of Nuclear Materials | 2015 | 5 Pages |
Abstract
The authors fabricated U-20Â wt.%Pu-2Â wt.%Am-10Â wt.%Zr alloys and evaluated the heat capacity and thermal conductivity. The heat capacity was measured between 335 and 827Â K by a drop calorimetry. The thermal diffusivity was measured between 300 and 1073Â K by a laser flash method. The thermal conductivity was evaluated from the measured thermal diffusivity and heat capacity. The thermal conductivity of U-20Â wt.%Pu-2Â wt.%Am-10Â wt.%Zr alloy was slightly higher than literature values of U-Pu-Zr and U-Pu-MA-Zr alloys. The thermal conductivity was formulated for use in practical design for Generation IV fast reactors.
Related Topics
Physical Sciences and Engineering
Energy
Nuclear Energy and Engineering
Authors
Tsuyoshi Nishi, Kunihisa Nakajima, Masahide Takano, Masaki Kurata, Yuji Arita,