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Abstract

Ion chromatography (IC) coupled to inductively coupled plasma-mass spectrometry (ICP-MS) was applied to the characterization of 2 different spent fuel samples, uranium oxide (UO(2)) and mixed uranium-plutonium oxide (MOX) and the results were compared with those obtained by other techniques. Isotope dilution analysis with ion chromatographic separation was applied to the determination of the fission products. The standard additions method was employed for the determination of monoisotopic fission products and actinides. Based on the isotope dilution-thermal ionisation mass spectrometry (ID-TIMS) results for U, Pu and 148-Nd, fuel burn-up was calculated and the value introduced into 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.

Additional information

Authors: BARRERO MORENO J M, JRC Karlsruhe (DE);GARCIA ALONSO J I, ;ARBORE P, ;NICOLAOU G, ;KOCH L,
Bibliographic Reference: Paper presented: 1995 European Winter Conference on Plasma Spectrochemistry, Cambridge (GB), January 1995
Availability: Available from (1) as Paper EN 38857 ORA
Record Number: 199710195 / Last updated on: 1997-04-01
Category: PUBLICATION
Original language: en
Available languages: en
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