COMPREHENSIVE ACTINIDE ANALYSIS OF SPENT NUCLEAR FUELS
The quantitative determination of uranium and plutonium isotopes is achieved by isotope dilution analyses using 233-U and 244-Pu as spike isotopes. The separation is accomplished by ion exchange from 8 M HNO-3. The less abundant nuclides 232-U and 236-Pu, which are in the ppb range, require an additional purification which is carried out by anion exchange in HBr medium. Their concentrations are determined in the alpha spectrum relative to the major isotopes previously determined by isotope dilution mass spectrometry. An example of the results of a post-irradiation analysis is given for samples from a fuel element stemming from the light water reactor KWO Obrigheim, FRG. Two types of material were analyzed: standard 235-U enriched fuel and a mixed oxide fuel containing 3% plutonium. The concentration of the analyzed actinides extended over a range of 10 orders of magnitude. The relative standard deviation of the concentrations determined from replicate measurements varied between point 0.1 and 20%.
Bibliographic Reference: 10TH INTERNATIONAL MASS SPECTROMETRY CONFERENCE, SWANSEA (UK), SEPT. 9-13, 1985 WRITE TO CEC LUXEMBOURG, DG XIII/A2, POB 1907 MENTIONING PAPER E 32427 ORA
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Record Number: 1989124062800 / Last updated on: 1987-01-01
Available languages: en