Releasing Behavior of Tritium from Neutron Irradiated Borosilicate Glass
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Published:1982
Issue:
Volume:15
Page:
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ISSN:0272-9172
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Container-title:MRS Proceedings
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language:en
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Short-container-title:MRS Proc.
Author:
Yamamoto Yoshimasa,Kitagawa Kazuo,Atsumi Hisao,Yamanaka Shinsuke,Miyake Masanobu
Abstract
ABSTRACTSpecimens of borosilicate glass were irradiated in a material testing reactor at a neutron fluence of 1019–1020 nvt and a temperature of below 250°c. Tritium released from the specimen was determined by means of a specially designed sampling system and liquid scintillation counter.Temperature and time dependence of the releasing behavior of tritium from borosilicate glass was obtained in the temperature range of 200 – 700°C. Very small amount of tritium as compared with the amount contained in the specimen was released in several hours at temperatures below 700°C. The greater part of tritium released from the specimen was tritium oxide, which is controlled by the diffusion step of tritium in the specimen. The diffusion coefficient of tritium in borosilicate glass was also obtained, which agreed with that of water in glasses.
Publisher
Springer Science and Business Media LLC
Subject
General Engineering
Reference12 articles.
1. Tritium release from neutron-irradiated li2o; constant rate heating measurements
2. Permeation, Diffusion, and Solubility of Deuterium in Pyrex Glass
3. 8. Miyake M. Tech. Rep. of the Osaka Univ. in press (1982).
4. 7. Goles R. W. and Brauer F. P. , Proc. Int. Conf. on T. Tech. in Fusion, Fission and Isotopic Applications. P. 182 (1980).