Irradiation of lithium aluminate and tritium extraction

• Published in: Journal of nuclear materials Vol. 133; pp. 238 - 241
• Main Authors: Roth, E., Abassin, J.J., Botter, F., Briec, M., Chenebault, P., Masson, M., Rasneur, B., Roux, N.
• Format: Journal Article Conference Proceeding
• Language: English
• Published: Amsterdam Elsevier B.V 01.01.1985; Elsevier
• Subjects: Applied sciences; Controled nuclear fusion plants; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Installations for energy generation and conversion: thermal and electrical energy; Other techniques and industries; Irradiation; Nuclear fusion reactor; Tritium; Blanket; Extraction; Thermonuclear fusion
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/0022-3115(85)90142-4

Post-irradiation tritium extraction from γ-LiAlO 2, samples irradiated to 2 × 10 17 n/cm 2 in quartz ampoules produced mostly tritiated water. During in-pile experiments the sample container material influences the ratio of tritium gas to tritiated water. Stainless steel capsules yield more T 2 gas than quartz capsules probably because of a reduction process. Difficulties in interpretation arise from adsorption of tritiated water on the measuring lines. Both experiments showed that much faster extraction rates are obtained from small grain size than large grain size samples at the same open porosity. If diffusion in the grains controls the extraction rates, apparent D values vary from 10 16 to 1.5 × 10 −15 cm 2/s in the temperature range explored. Around 500°C small grain samples reached an equilibrium tritium concentration of a few mCi in 4 h. Such values are suitable for a blanket concept.