Back to Search
Start Over
Examination of UC-ZrC after long term irradiation at thermionic temperature
- Publication Year :
- 1972
- Publisher :
- United States: NASA Center for Aerospace Information (CASI), 1972.
-
Abstract
- Two fluoride tungsten clad UC-ZrC fueled capsules, designated as V-2C and V-2D, were examined a hot cell after irradiation in NASA Plum Brook Reactor at a maximum cladding temperature of 1930 K for 11,089 and 12,031 hours to burnups of 3.0 x 10 to the 20th power and 2.1 x 10 to the 20th power fission/c.c. respectively. Percentage of fission gas release from the fuel material was measured by radiochemical means. Cladding deformation, fuel-cladding interaction and microstructures of fuel, cladding, and fuel-cladding interface were studied metallographically. Compositions of dispersions in fuel, fuel matrix and fuel-cladding interaction layer were analyzed by electron microprobe techniques. Axial and radial distributions of burnup were determined by gamma-scan, autoradiography and isotopic burnup analysis. The results are presented and discussed in conjunction with the requirements of thermionic fuel elements for space power application.
- Subjects :
- Nuclear Engineering
Subjects
Details
- Language :
- English
- Database :
- NASA Technical Reports
- Notes :
- NAS3-15323, , PROJ. 0184
- Publication Type :
- Report
- Accession number :
- edsnas.19730005981
- Document Type :
- Report