Published March 2018 | Version v1
Journal article

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

  • 1. Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University, 744 Moto-oka, Nishi-ku, Fukuoka 819-0395 (Japan)
  • 2. Department of Advanced Energy Engineering Science, Kyushu University, 6-1 Kasuga-koen, Kasuga, Fukuoka 816-8580 (Japan)

Description

Highlights: • Surveillance of tritium contamination on tritium handling facility was performed. • Tritium released or leaked into the facility could cause uniform contamination. • Some of the highest tritium concentration were observed at the inside. - 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.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2017.04.013

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2017.04.013;
PII
S0920379617304088;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
128
Journal Page Range
p. 231-234
ISSN
0920-3796
CODEN
FEDEEE

Optional Information

Notes
© 2017 Elsevier B.V. All rights reserved.