Distribution of fission products in Peach Bottom HTGR fuel element E01-01
The fifth in a projected series of six postirradiation examinations of Peach Bottom High-Temperature Gas-Cooled Reactor driver fuel elements is described. The element analyzed received an equivalent of 897 full-power days of irradiation prior to the 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 20.3 Ci in the graphite sleeve and 8.1 Ci in the spine at the time of element withdrawal from the core. In addition, the nuclides /sup 134/Cs, /sup 110 m/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 four axial locations of the fueled region of the element sleeve and two axial locations of the element spine. 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:
- 6612567
- Report Number(s):
- ORNL/TM-6353; TRN: 79-001061
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
PEACH BOTTOM-1 REACTOR
SPENT FUEL ELEMENTS
FISSION PRODUCTS
GAMMA FUEL SCANNING
MATERIALS TESTING
METALLOGRAPHY
SPATIAL DISTRIBUTION
DISTRIBUTION
ENRICHED URANIUM REACTORS
FUEL ELEMENTS
FUEL SCANNING
GAMMA RADIOGRAPHY
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
INDUSTRIAL RADIOGRAPHY
ISOTOPES
NONDESTRUCTIVE TESTING
POWER REACTORS
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTORS
TESTING
THERMAL REACTORS
210300* - Power Reactors
Nonbreeding
Graphite Moderated