Modelling of Tritium Release from Irradiated Li₂ZrO₃

Release behavior of bred tritium from LiAlO2

“…3-5, respectively. It can been seen from comparison of these figures that the fastest tritium release is observed when the purge gas with water vapor is applied and a little slower release is observed when the purge gas with hydrogen is applied and much slower release is obtained in the case of the purge by dry gas, though the purge by hydrogen gives much slower release curve similar to the purge by dry gas at tritium release from Li 4 SiO 4 , Li 2 TiO 3 and Li 2 ZrO 3 as reported by the present authors [12,13]. It is mentioned in the previous report by the present authors about the tritium inventory in a LiAlO 2 blanket that LiAlO 2 has a rather large isotope exchange capacity other than the adsorption capacity on the grain surface [4].…”

“…The sample irradiated only for 3 min was taken for the fitting object in this figure expecting that irradiation for 3 min did not create enough defects to give effect on tritium diffusion. The modified method [15] of the way proposed by Beloglazov et al for Li 2 ZrO 3 [12] was applied in this study taking the isotope exchange capacity on the grain surface and a good fitting was obtained as shown in Fig. 6.…”

Modeling of HT and HTO release from irradiated lithium metazirconate

“…The tritium release in the presence of water in the purge gas was studied in a previous paper [2], by assuming that bulk diffusion and isotope exchange reaction (2) were the rate-determining steps. The diffusivity was assumed to be a simple Arrhenius type temperature dependence while the mass transfer coefficient of the isotope exchange reaction (2), K F;ex2 was assumed to be constant [10].…”

“…In the previous study [2] numerical modeling of tritium release spectra from irradiated Li 2 ZrO 3 was performed considering the diffusion of tritium in the bulk of grains, adsorption/desorption of water on the surface of grains and isotope exchange reaction between water vapor in the gas stream and tritium on grain surfaces. The tritium release kinetics were interpreted by assuming that bulk diffusion and isotope exchange reaction were the rate-determining steps in the presence of water in the purge gas.…”

Estimation of tritium release behavior from solid breeder materials under the condition of ITER test blanket module

“…To analyze the effects of the surface reactions on tritium release behavior from solid breeder materials, tritium release experiments were carried out using a purge gas with different compositions (dry N 2 , N 2 with H 2 , N 2 with H 2 O) while applying the out-pile temperature programmed desorption techniques at the Japan Atomic Energy Research Institute (JAERI) [1][2][3][4].…”