Fig.4-17 Separation mechanism of high-purity Pd by laser irradiation and its operating procedure
Table 4-3 Contamination rates of major constituents of spent nuclear fuel in Pd precipitate
Palladium-107 (107Pd), which is one of the radionuclides generated by nuclear fission of uranium, is found in spent nuclear fuel. Due to its extremely long half-life of about 6.5 × 106 years, 107Pd can be potentially harmful to human body over a long period of time. The long-term risks involved in 107Pd radiation are basically estimated based on the 107Pd content in spent nuclear fuel. However, predicted values provided through theoretical calculation have been used instead of the measured content of 107Pd because of the lack of published information concerning 107Pd quantitation.
Accurate measurement of 107Pd can only be achieved by a separation technique which allows recovery of high-purity Pd from spent nuclear fuel. Chromatographic separation using adsorbent-packed columns, which is the most commonly applied technique, is inevitably associated with numerous operational steps, making it hard to complete the separation in a short time. Additionally, continuous work with highly radioactive samples, such as a spent nuclear-fuel solution, causes undesirable radiation exposure to workers.
The separation technique developed in this study enables selective recovery of Pd by a simple operation, leading to the world’s first successful quantitation of 107Pd in spent nuclear fuel. Precipitation of Pd is induced by irradiation by a pulsed laser of wavelength 355 nm (Fig.4-17). The precipitation reaction is completed in 20 minutes in a closed vessel and operators can keep their distance from a sample during irradiation. This can help minimize the contamination of laboratory facilities and radiation exposure to workers during irradiation.
The resulting Pd precipitate was dissolved with aqua regia (a mixture of nitric acid and hydrochloric acids) and measured by inductively coupled plasma-mass spectrometry. Almost none of the elements initially present were detected in the precipitate (Table 4-3) and Pd was recovered with a purity above 99.9%. With the perfect removal of all interfering components, 107Pd in spent nuclear fuel was accurately measured.
Application of the developed technique to other samples, for example, high-level radioactive waste (HLW), is expected. We are trying to expand the versatility of our technique for application to HLW, which has a complicated chemical composition. We will make continuous efforts to establish highly reliable safety assessment of HLW disposal by offering accurate measurements of 107Pd.