| Budget Amount *help |
¥12,090,000 (Direct Cost: ¥9,300,000、Indirect Cost: ¥2,790,000)
Fiscal Year 2013: ¥2,730,000 (Direct Cost: ¥2,100,000、Indirect Cost: ¥630,000)
Fiscal Year 2012: ¥3,640,000 (Direct Cost: ¥2,800,000、Indirect Cost: ¥840,000)
Fiscal Year 2011: ¥5,720,000 (Direct Cost: ¥4,400,000、Indirect Cost: ¥1,320,000)
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| Research Abstract |
Zr-based alloys are widely used for fuel claddings of light water reactors. These alloys might fail to confine fuel elements and fission products when absorbing a large amount of hydrogen. In the present work, deuterium depth profiles in oxides formed on the surface of the alloys were observed with a good depth resolution. The results showed that (1) the hydrogen absorption rate of the alloys was controlled by the hydrogen diffusion coefficient in the oxide, (2) the inner region of the oxide near the oxide/metal interface inhibited the hydrogen absorption owing to a very low diffusion coefficient, and (3) the inner region with the low diffusivity became larger with irradiation dose, probably due to formation of irradiation defects such as dislocation loops.
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