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Title: Determination of iodine-129 in mixed fission products by neutron activation analysis

Technical Report ·
DOI:https://doi.org/10.2172/7084087· OSTI ID:7084087

This report describes an improved method for analyzing /sup 129/I in fission product mixtures originating from fuel reprocessing studies. The method utilizes conventional iodine valence adjustment and solvent extraction techniques to chemically separate /sup 129/I from most fission products. The /sup 129/I is then determined by neutron irradiation and measurement of the 12.4-h /sup 130/I produced by the neutron capture reaction. Special techniques were devised for neutron irradiation of /sup 129/I samples in the pneumatic tube irradiation facilities at the High Flux Isotope (HFIR) and Oak Ridge Research (ORR) reactors. Chemically separated /sup 129/I is adsorbed on an anion exchange resin column made from an irradiation container. The loaded resin is then irradiated in either of the pneumatic facilities to produce /sup 130/I. Sensitivity of the analysis with the HFIR facility (flux: 5 x 10/sup 14/ neutrons cm/sup -2/s/sup -1/) and a 100-s irradiation time is approximately 2 ng. Samples up to 250 mL in volume can be easily processed. The method has been in routine use for about two years and has given good results on samples of reactor fuel solutions and off-gas traps.

Research Organization:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
DOE Contract Number:
W-7405-ENG-26
OSTI ID:
7084087
Report Number(s):
ORNL/TM-7449; TRN: 80-019297
Country of Publication:
United States
Language:
English