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Releasing Behavior of Tritium from Neutron Irradiated Borosilicate Glass

Published online by Cambridge University Press:  21 February 2011

Yoshimasa Yamamoto ,
Kazuo Kitagawa ,
Hisao Atsumi ,
Shinsuke Yamanaka  and
Masanobu Miyake
Yoshimasa Yamamoto
Affiliation:
Mechanical Engineering Research Laboratory, Kobe Steel, Ltd., 651 Chuo-ku, Kobe, Japan
Kazuo Kitagawa
Affiliation:
Mechanical Engineering Research Laboratory, Kobe Steel, Ltd., 651 Chuo-ku, Kobe, Japan
Hisao Atsumi
Affiliation:
Department of Nuclear Engineering, Osaka University, 565 Yamadaoka, Suita, Osaka, Japan
Shinsuke Yamanaka
Affiliation:
Department of Nuclear Engineering, Osaka University, 565 Yamadaoka, Suita, Osaka, Japan
Masanobu Miyake
Affiliation:
Department of Nuclear Engineering, Osaka University, 565 Yamadaoka, Suita, Osaka, Japan
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Abstract

Specimens 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.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 15: Symposium D – Scientific Basis for Nuclear Waste Management VI , 1982 , 191
Copyright
Copyright © Materials Research Society 1983

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References

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