Disposal procedure for contaminated surface of tritium handling facility in the decommissioning operation

Toshiharu Takeishi; Kazuya Furuichi; Kazunari Katayama; Yoshiya Kawabata; Satoshi Fukada

doi:10.1016/j.fusengdes.2017.04.013

Disposal procedure for contaminated surface of tritium handling facility in the decommissioning operation

Toshiharu Takeishi, Kazuya Furuichi, Kazunari Katayama, Yoshiya Kawabata, Satoshi Fukada

Engineering Science for Advanced energy system

Research output: Contribution to journal › Article › peer-review

1 Citation (Scopus)

Abstract

For the decommissioning operation of tritium handling facility, surveillance of contamination with tritium on floor, wall and roof was performed. Significant amount of tritium contamination was detected in approximately 86% of total surface measurement points and maximally 70 mm of scraping was required to eliminate tritium contamination. In some samples for measurement of tritium depth profile, the highest tritium concentration was observed at the inside but not the surface. This measurement result of depth profile is also discussed with our previous calculation results considering diffusion, adsorption, desorption of tritium in the concrete and isotope exchange reaction between tritiated water vapor in the concrete bulk and atmospheric water vapor.

Original language	English
Pages (from-to)	231-234
Number of pages	4
Journal	Fusion Engineering and Design
Volume	128
DOIs	https://doi.org/10.1016/j.fusengdes.2017.04.013
Publication status	Published - Mar 2018

All Science Journal Classification (ASJC) codes

Civil and Structural Engineering
Nuclear Energy and Engineering
Materials Science(all)
Mechanical Engineering

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10.1016/j.fusengdes.2017.04.013

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title = "Disposal procedure for contaminated surface of tritium handling facility in the decommissioning operation",

abstract = "For the decommissioning operation of tritium handling facility, surveillance of contamination with tritium on floor, wall and roof was performed. Significant amount of tritium contamination was detected in approximately 86% of total surface measurement points and maximally 70 mm of scraping was required to eliminate tritium contamination. In some samples for measurement of tritium depth profile, the highest tritium concentration was observed at the inside but not the surface. This measurement result of depth profile is also discussed with our previous calculation results considering diffusion, adsorption, desorption of tritium in the concrete and isotope exchange reaction between tritiated water vapor in the concrete bulk and atmospheric water vapor.",

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AU - Takeishi, Toshiharu

AU - Furuichi, Kazuya

AU - Katayama, Kazunari

AU - Kawabata, Yoshiya

AU - Fukada, Satoshi

PY - 2018/3

Y1 - 2018/3

N2 - For the decommissioning operation of tritium handling facility, surveillance of contamination with tritium on floor, wall and roof was performed. Significant amount of tritium contamination was detected in approximately 86% of total surface measurement points and maximally 70 mm of scraping was required to eliminate tritium contamination. In some samples for measurement of tritium depth profile, the highest tritium concentration was observed at the inside but not the surface. This measurement result of depth profile is also discussed with our previous calculation results considering diffusion, adsorption, desorption of tritium in the concrete and isotope exchange reaction between tritiated water vapor in the concrete bulk and atmospheric water vapor.

AB - For the decommissioning operation of tritium handling facility, surveillance of contamination with tritium on floor, wall and roof was performed. Significant amount of tritium contamination was detected in approximately 86% of total surface measurement points and maximally 70 mm of scraping was required to eliminate tritium contamination. In some samples for measurement of tritium depth profile, the highest tritium concentration was observed at the inside but not the surface. This measurement result of depth profile is also discussed with our previous calculation results considering diffusion, adsorption, desorption of tritium in the concrete and isotope exchange reaction between tritiated water vapor in the concrete bulk and atmospheric water vapor.

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JO - Fusion Engineering and Design

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Disposal procedure for contaminated surface of tritium handling facility in the decommissioning operation

Abstract

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