We found a match
Your institution may have access to this item. Find your institution then sign in to continue.
- Title
Separation and quantification of chemically diverse analytes in neutron irradiated fissile materials.
- Authors
Douglas, M.; Friese, J. I.; Greenwood, L. R.; Farmer, III, O. T.; Thomas, M. L.; Maiti, T. C.; Finn, E. C.; Garofoli, S. J.; Gassman, P. L.; Huff, M. M.; Schulte, S. M.; Smith, S. C.; Thomas, K. K.; Bachelor, P. P.
- Abstract
Quantitative measurement of fission and activation products resulting from neutron irradiation of fissile materials is of interest for applications in environmental monitoring, nuclear waste management, and national security. Based on established separation processes involving co-precipitation, solvent extraction, and ion-exchange and extraction chromatography, we have optimized a proposed sequence of separation steps to allow for the timely quantification of analytes of interest. We have recently evaluated this scheme using an irradiated sample to examine the adequacy of separations for measurement of desired analytes by gamma spectrometry. Here we present the radiochemical separations utilized and the yields and purity obtained.
- Subjects
FISSION (Asexual reproduction); NEUTRON irradiation; CHROMATOGRAPHIC analysis; GAMMA ray spectrometry; RADIOCHEMICAL research
- Publication
Journal of Radioanalytical & Nuclear Chemistry, 2009, Vol 282, Issue 1, p63
- ISSN
0236-5731
- Publication type
Article
- DOI
10.1007/s10967-009-0263-8