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Abstract

In-situ tritium release experiments have been performed on samples of Li(2)ZrO(3), Li(6)Zr(2)O(7) and Li(6)ZrO(6) contained in vented capsules. Irradiation was carried out in the High Flux Reactor (HFR) at Petten during 97 full power days. The capsules were purged with Helium +0.1 vol.%H(2). During the irradiation several temperature transients were performed and the corresponding tritium release measured. Tritium residence times were determined using the diffusion and first order desorption model. A tritium residence time of 1 day was achieved at temperatures of approximately 560 C for Li(6)ZrO(6), 400 C for Li(2)ZrO(3) (85% TD) and << 350 C for Li(6)Zr(2)O(7). The grain size and open porosity value, which differ for the various materials, have a significant influence on the tritium residence time.

Additional information

Authors: KWAST H, Netherlands Energy Research Foundation, ECN, Petten (NL);ELEN J D, Netherlands Energy Research Foundation, ECN, Petten (NL);CONRAD R, JRC Petten Estab. (NL);DEBARBERIS L, JRC Petten Estab. (NL);KENNEDY P, Northern Research Laboratories, Springfields (GB);FLIPOT A J, SCK/CEN, Mol (BE)
Bibliographic Reference: Paper presented: 15th SOFT Conference, Utrecht (NL), Sept. 19-23, 1988
Availability: Available from (1) as Paper EN 34120 ORA
Record Number: 198910140 / Last updated on: 1994-12-01
Category: PUBLICATION
Original language: en
Available languages: en
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