Distribution of fission products in Peach Bottom HTGR fuel element E11-07
This is the second in a projected series of six post-irradiation examinations of Peach Bottom High-Temperature Gas-Cooled Reactor driver fuel elements. Element E11-07, the subject of this report, received an equivalent of 701 full-power days of irradiation prior to scheduled withdrawal. 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 17 Ci in the graphite sleeve and 8.3 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 distribution of the beta emitters /sup 3/H, /sup 14/C, and /sup 90/Sr were obtained at six axial locations, four within the fueled region and one each above and below. The radial dissection was accomplished by use of a manipulator-operated lathe in a hot cell. These profiles reveal an increased degree of penetration of /sup 134/Cs, relative to /sup 137/Cs, evidently due to a longer time spent as xenon precursor. In addition to fission product distribution, the appearance of the element components 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:
- 7312373
- Report Number(s):
- ORNL-5214; TRN: 77-011264
- Country of Publication:
- United States
- Language:
- English
Similar Records
Distribution of fission products in Peach Bottom HTGR fuel element E01-01
Distribution of fission products in Peach Bottom HTGR fuel element F03-01
Related Subjects
PEACH BOTTOM-1 REACTOR
FUEL ELEMENTS
DISTRIBUTION
FISSION PRODUCTS
GAMMA FUEL SCANNING
ENRICHED URANIUM REACTORS
FUEL SCANNING
GAMMA RADIOGRAPHY
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
INDUSTRIAL RADIOGRAPHY
ISOTOPES
MATERIALS TESTING
NONDESTRUCTIVE TESTING
POWER REACTORS
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTORS
TESTING
THERMAL REACTORS
210300* - Power Reactors
Nonbreeding
Graphite Moderated