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Used cladding hulls from pressurized water reactor (PWR) are characterized to provide useful information for the treatment and disposal of cladding hull wastes. The radioactivity and the mass of gamma emitting nuclides increases with an increase in the fuel burn-up and their removal ratios are found to be more than 99 wt.% except Co-60 and Cs-137. In the result of measuring the concentrations of U and Pu included in the cladding hull wastes, most of the residues are remained on the surface and the removal ratio of U and Pu are revealed to be over 99.98 wt.% for the fuel burn-up of 35,000 MWd/tU. An electron probe micro-analyzer (EPMA) line scanning shows that radioactive fission products are penetrated into the Zr oxide layer, which is proportional to the fuel burn-up. The oxidative decladding process exhibits more efficient removal ratio of radionuclides.

Abstract: Cerium-substituted bismuth titanate (Bi3.25Ce0.75Ti3O12 (BCT)) films were deposited on the Pt(111)/SiO2/Si(100) substrates by a liquid source misted chemical deposition technique. This film showed X-ray diffraction patterns that crystallization along the (006) direction was suppressed and did not contain any other oxides. The remnant polarization of this film increased with increase in annealing temperature. The 2P r and 2E c values of the BCT film annealed at 700 °C were 19.72 μC/cm2 and 357 kV/cm, respectively. 2P r value of this film decreased by less than 5% of the initial value after 7×109 read/write switching cycles at a frequency of 1 MHz. [Copyright &y& Elsevier]