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Title: Distribution of fission products in Peach Bottom HTGR fuel element E14-01

Technical Report ·
DOI:https://doi.org/10.2172/7088983· OSTI ID:7088983

The third in a projected series of six postirradiation examinations of Peach Bottom High-Temperature Gas-Cooled Reactor driver fuel elements is presented. Element E14-01, the subject of the report, was one of the 60 driver elements (out of a total of 804) that contained zirconium boride pellets within a hollow spine. It was also one of the few predimensioned elements, which therefore allowed accurate determination of dimensional change due to irradiation service. The element received an equivalent of 897 full-power days irradiation prior to scheduled termination of Core 2 operation. The examination procedures emphasized the determination of fission product distributions in the graphite portions of the fuel element. Continuous axial scans indicated a /sup 137/Cs inventory of 0.24 Ci in the graphite sleeve and 0.047 Ci in the spine at the time of element withdrawal from the core. In addition, the nuclides /sup 134/Cs, /sup 110m/Ag, /sup 60/Co, and /sup 154/Eu were found in the graphite portions of the fuel element in significant amounts. Radial distributions of these nuclides plus the beta-emitters /sup 3/H, /sup 14/C, and /sup 90/Sr were obtained at three axial locations within the fueled region of the element. The radial dissection was accomplished by use of a manipulator-operated lathe in a hot cell. In addition to fission product distributions, the appearance of the component parts of the element was recorded photographically, fuel compact and graphite dimensions were recorded at numerous locations, and metallographic examinations of the fuel were performed.

Research Organization:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
DOE Contract Number:
W-7405-ENG-26
OSTI ID:
7088983
Report Number(s):
ORNL/TM-5730; TRN: 77-018825
Country of Publication:
United States
Language:
English