Published March 2012 | Version v1
Miscellaneous

Thermal and mechanical properties of zirconium hydrides with various hafnium contents

  • 1. Osaka Univ., Graduate School of Engineering, Suita, Osaka (Japan)
  • 2. Tohoku Univ., Institute for Materials Research, Oarai, Ibaraki (Japan)

Description

Zirconium (Zr) hydride is currently expected as a neutron shield material for fast reactors. In order to evaluate safety and economic efficiency of the nuclear reactor, the thermal and mechanical properties of the hydride should be understood. In addition, since chemical properties of Zr and hafnium (Hf) are quite similar, Zr contains a few percent Hf generally. Therefore, it is very important to evaluate the effect of Hf content on the properties of Zr hydride. In the present study, fine bulk samples of δ-phase Zr hydrides with various Hf contents were prepared and their thermal and mechanical properties were investigated. We examined the phase states and the microstructure of the hydrides by means of X-ray diffraction and SEM/EDX analyses. In the temperature range from room temperature to 673 K, the heat capacity and the thermal diffusivity of the hydrides were measured and the thermal conductivity was evaluated. The Vickers hardness and the sound velocity of the hydrides were measured at room temperature, and the elastic modulus was calculated from the measured sound velocity. The effects of temperature and Hf content on the properties of Zr hydrides were studied. (author)

Part of:
1st Asian nuclear fuel conference (ANFC 2012)

Additional details

Publishing Information

Imprint Title
1st Asian nuclear fuel conference (ANFC 2012)
Imprint Pagination
112 p.
Journal Page Range
p. 68-69

Conference

Title
1. Asian nuclear fuel conference
Acronym
ANFC 2012
Dates
22-23 Mar 2012
Place
Osaka (Japan)

Optional Information

Notes
3 refs., 3 figs.