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Modelling of Tritium Release from Irradiated Li2ZrO3

S.Beloglazov, M.Nishikawa, T.Tanifuji

Fusion Science and Technology / Volume 41 / Number 3P2 / May 2002 / Pages 1049-1053

Blanket Material and Process / Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 / dx.doi.org/10.13182/FST02-A22744

In this paper we propose a model to explain tritium release from irradiated Li2ZrO3 sample made by Mitsubishi Atomic Power Industries Inc. (MAPI). The release curves were obtained by temperature programmed desorption (TPD) techniques in a series of experiments in Kyoto University Reactor (KUR) and in the JRR-4 reactor of the Japan Atomic Energy Research Institute (JAERI). In the model a number of mass transfer steps were taken into account. There were diffusion of tritium in the grain, adsorption and desorption of water on the surface of grains, two types of isotope exchange reactions, water formation reaction in addition of hydrogen to the purge gas. Tritium release curves for different purge gas compositions (N2, N2 + H2O) were calculated to compare with data obtained in the experiments. Apparent diffusivities of tritium in crystal grain of Li2ZrO3 were determined.