December 15, 2020
Journal Article

A quantitative study of retention and release of deuterium and tritium during irradiation of y-LiAlO2 pellets

Abstract

This study reports on the quantification of deuterium in ion-irradiated gamma-LiAlO2 pellets as a function of dose and temperature. The gamma-LiAlO2 pellets were sequentially irradiated with He+ and D2+ ions to the same fluences of 5E16, 1E17 and 2E17 He++D+/cm2 at 188 K. Additional irradiation was performed to 1E17, 2E17 and 4E17 He++D+/cm2 at 573 K. A set of the pellets irradiated at 188 K was shipped and stored at low temperatures from 80 to 132 K and characterized using time-of-flight secondary ion mass spectrometry at ~173 K. The deuterium depth profiles show a Gaussian-like distribution in the low-temperature pellets. The total deuterium retention is found to be directly proportional to the ion fluence. About 27 at.% of the implanted deuterium atoms were released from the pellet irradiated to 2E17 He++D+/cm2 at 188 K during storage at room temperature for ~1 month. Retention of the trapped or bound deuterium during ion irradiation at 573 K increases initially with ion fluence and tends to saturate at a high fluence. The amount of the released deuterium is observed to be quantitatively consistent with that of the released tritium from similar standard pellets during neutron irradiation at 573 K.

Revised: November 30, 2020 | Published: December 15, 2020

Citation

Jiang W., W.G. Luscher, T. Wang, Z. Zhu, L. Shao, and D.J. Senor. 2020. A quantitative study of retention and release of deuterium and tritium during irradiation of y-LiAlO2 pellets. Journal of Nuclear Materials 542. PNNL-SA-154763. doi:10.1016/j.jnucmat.2020.152532