Published March 1976 | Version v1
Report

Neutron irradiation damage in Al2O3 and Y2O3

  • 1. Los Alamos Scientific Lab., NM

Description

Two ceramics under consideration for use in fusion reactors, Al2O3 and Y2O3, were irradiated in the EBR-II fission reactor at 650, 875, and 10250K to fluences between 2 and 6 x 1021 n/cm2 (E greater than 0.1 MeV). Samples evaluated include sapphire, Lucalox, alumina, Y2O3, and Y2O3-10 percent ZrO2 (Yttralox). All Al2O3 specimens swelled significantly (1 to 3 percent), with most of the growth observed in sapphire along the c-axis at the higher temperatures. Al2O3 samples irradiated at 875 and 10250K contained a high density of small aligned ''pores''. Irradiated Y2O3-based ceramics exhibited dimensional stability and a defect content consisting primarily of unresolved damage and/or dislocation loops. The behavior of these ceramics under irradiation is discussed, and the relevance of fission neutron damage studies to fusion reactor applications is considered

Additional details

Publishing Information

Imprint Title
Radiation effects and tritium technology for fusion reactors. Vol. II
Imprint Pagination
p. II.498-II.516.
Report number
CONF-750989--P2

Conference

Title
International conference on radiation effects and tritium technology for fusion reactors.
Dates
30 Sep 1975.
Place
Gatlinburg, Tennessee, USA.