Characterization of Spent Nuclear Fuels by Ion Chromatography ICP-MS
Ion chromatography coupled to inductively coupled plasma-mass spectrometry (ICP-MS) has been applied for the characterization of 2 different spent fuel samples (uranium oxide (UO(2)) and mixed uranium-plutonium oxide (MOX)) and the results compared with other techniques. Isotope dilution analysis applying ion chromatographic separation was applied for the determination of the fission products (Rb, Sr, Cs, Ce, Nd, Sm, Eu and Gd). Standard additions method was employed for the determination of monoisotopic fission products and actinides. Total U and Pu were determined only by isotope dilution thermal ionization mass spectrometry (ID-TIMS). Nd, Am and Cm isotope concentrations were determined also by ID-TIMS. (144)Ce, (154)Eu, (134)Cs and (137)Cs were determined in parallel by gamma-spectrometry. Based on the ID-TIMS results for U, Pu and (148)Nd, fuel burn-up was calculated and the value introduced in the computer code KORIGEN in order to calculate the complete fuel inventory based on the known irradiation parameters for the 2 fuels. The agreement between the experimental IC-ICP-MS results and the theoretical calculations was within 15% for most isotopes.
Bibliographic Reference: Article: Journal of Analytical Atomic Spectrometry (1996)
Record Number: 199610489 / Last updated on: 1996-05-20
Original language: en
Available languages: en