Distribution of fission products in Peach Bottom HTGR fuel element E01-01
Description
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 137Cs 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 134Cs, /sup 110 m/Ag, 60Co, and 154Eu were found in the graphite portions of the fuel element in significant amounts. Radial distributions of these nuclides plus the beta-emitters 3H, 14C, and 90Sr 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
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A13/MF A01.
Files
Additional details
Publishing Information
- Imprint Pagination
- 280 p.
- Report number
- ORNL/TM--6353
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10441856
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FISSION PRODUCTS; GAMMA FUEL SCANNING; MATERIALS TESTING; METALLOGRAPHY; PEACH BOTTOM-1 REACTOR; SPATIAL DISTRIBUTION; SPENT FUEL ELEMENTS
- Descriptors DEC
- DISTRIBUTION; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; FUEL SCANNING; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; ISOTOPES; POWER REACTORS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTORS; TESTING; THERMAL REACTORS