Author/Authors :
Kakiuchi، نويسنده , , Kazuo and Itagaki، نويسنده , , Noboru and Furuya، نويسنده , , Takemi and Hattori، نويسنده , , Toshiitsu and Nakazono، نويسنده , , Yoshihisa and Ono، نويسنده , , Futaba and Yamaguchi، نويسنده , , Kenji and Yamawaki، نويسنده , , Michio، نويسنده ,
Abstract :
Hydride fuel of 45% U–ZrH1.6 was fabricated and the measurement of its thermal properties was carried out. The thermal conductivity of 45% U–ZrH1.6 in the range of room temperature −773 K was evaluated to be about three times higher than that of UO2 and nearly independent of temperature. Such a high thermal conductivity is favorable when this material is used as nuclear fuel. The pressure–composition–temperature (P–C–T) characteristics of UZr alloy hydrogen system were different from that of pure Zr. A plateau of the hydrogen pressure was found for H concentration (relative to the Zr concentration) between 0.2 and 0.6 for all temperature below 1173 K. This plateau region was attributed to UZr hydride formation from the UZr alloy. Over the plateau region in H concentration from 1.0 to 1.4, the equilibrium hydrogen pressure was a little higher than that of pure Zr, which was attributed to the reduced activity of Zr in UZr alloy. The activity of Zr calculated from the equilibrium hydrogen pressure was 0.90 at 1073 K, and 0.83 at 973 K.
