SOME STUDIES ON THE URANIUM-MOLYBDENUM ALLOY (in Japanese)
U-Mo alloy is of interest as power-reactor fuel. The characteristic behavior of the alloy when subjected to certain heat treatments and its general properties were investigated. The specimens were made by vacuum induction melting and were rolled at 600 and 900 deg C. In the heat treatment tests, the phase changes by quenching from various high temperature phases, the effects of quenching rate from gamma phase range, and Ms temperature for 1.30% Mo alloy were studied. Thermal cycling test revealed that greater improvement was obtained by gamma quenching followed hy alpha annealing for the rolled rods with Mo content ranglng from 0.5 to 9.0%. Oxidation test in air at 300, 400, and 500 deg C had shown that the rate constant of oxidation decreased with increasing Mo contents in the lower Mo range, but it increased as Mo contents became higher. The same tendency was observed on the corrosion test in hot water. The minimum weight loss in 350 deg C hot water could be obtained at 12 wt.% Mo. (auth)
- Research Organization:
- Atomic Energy Research Inst., Tokyo; Mitsubishi Metal Mining Co., Japan; Atomic Fuel Corp., Tokyo
- Sponsoring Organization:
- USDOE
- NSA Number:
- NSA-14-014086
- OSTI ID:
- 4189443
- Journal Information:
- J. Atomic Energy Soc. Japan, Journal Name: J. Atomic Energy Soc. Japan Vol. Vol: 2
- Country of Publication:
- Country unknown/Code not available
- Language:
- Japanese
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