학술논문
Fabrication, irradiation, and irradiation damage studies of a high-temperature fuel element material. Final Report, March 9, 1961 to June 30, 1961
Document Type
Technical Report
Author
Source
Other Information: Orig. Receipt Date: 31-DEC-63
Subject
Language
English
Abstract
BS>Specimens of UBe13-- ZrBe13 solid solutions were prepared for preirradiation and irradiation studies. Specimens containing 5, 10, and 20 wt percent uraniuin of 20% enrichment were submitted to ORNL for further study. Capsules for irradiating test specimens were designed, fabricated, and tested. Corrosion studies of the specimens submerged in NaK and sealed in the capsule were conducted at temperatures anticipated during irradiation in the MTR. No significant reaction occurred under these conditions. Techniques were developed for examining specimens fabricated. Studies of raw materials and fabricated specimens by x-ray diffraction, metallography, and chemical analyses of etching solutions indicate fabricated specimens are essentially solid solutions of UBe13 in ZrBe13. Small quantities of free beryllium were detected in all specimens. Properties of fabricated specimens reported include density, modulus of rupture, hardness, grain size, chemical compositions, and corrosion resistance in NaK and air.