Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Some studies on the oxidation states of fission-product iodine (/sup 129/I) in irradiated UO/sub 2/ (LWBR Development Program)

Technical Report ·
OSTI ID:7092080
Both the UO/sub 2/ fuel and Zircaloy cladding from seven irradiated (approximately 5 x 10/sup 20/ fissions/cm/sup 3/) PWR blanket rods were leached, first with methyl chloroform to extract any free iodine, followed by a second extraction with water to collect iodide and iodate ions. Only trace amounts of /sup 129/I activity were detected in the organic leaching solutions, but definite /sup 129/I peaks were identified in the water leachings of the UO/sub 2/ fuel from one rod. Further leachings with HCl solutions increased the amount of /sup 129/I extracted. It was concluded that, for the quantity of /sup 129/I leached from the irradiated UO/sub 2/, the major fraction is in the combined iodine (probably as iodide) rather than in the free iodine elemental state. The dominant amount of iodine is most likely tightly chemically bound, probably with metallic fission products. This appears reasonable because the oxidation reaction between unirradiated UO/sub 2/ and I/sub 2/, as evidenced by x-ray diffraction measurements, would permit the reduction to iodide of any fission-product free iodine produced by fissioning. (NSA 23: 47371)
Research Organization:
Bettis Atomic Power Lab., Pittsburgh, PA (USA)
DOE Contract Number:
AT(11-1)-GEN-14
OSTI ID:
7092080
Report Number(s):
WAPD-TM-851
Country of Publication:
United States
Language:
English

Similar Records