Published March 2015 | Version v1
Journal article

Behaviour of tritium in the vacuum vessel of JT-60U

  • 1. JT-60 Safety Assessment Group, JAEA, Mukoyama (Japan)
  • 2. Hydrogen Isotope Research Center, University of Toyama, Gofuku (Japan)
  • 3. ITER Project Management Group, JAEA, Mukoyama (Japan)

Description

The disassembly of the JT-60U torus started in 2010 after 18 years of deuterium plasma operations. The vessel is made of Inconel 625. Therefore, it was very important to study the hydrogen isotope (particularly tritium) behavior in Inconel 625 from the viewpoint of the clearance procedure. Inconel 625 specimen was exposed to the D2 (92.8 %) - T2 (7.2 %) gas mixture at 573 K for 5 hours. The tritium release from the specimen at 298 K was controlled for about 1 year. After that a part of tritium remaining in the specimen was released by heating up to 1073 K. Other part of tritium trapped in the specimen was measured by chemical etching method. Most of the chemical form of the released tritium was HTO. The contaminated specimen by tritium was released continuously the diffusible tritium under the ambient condition. In the tritium release experiment, the amount of desorbed tritium was about 99% during 1 year. It was considered that the tritium in Inconel 625 was released easily

Availability note (English)

Available from doi: http://dx.doi.org/10.13182/FST14-T46

Additional details

Identifiers

Publishing Information

Journal Title
Fusion Science and Technology
Journal Volume
67
Journal Issue
2
Journal Page Range
p. 428-431
ISSN
1536-1055

Conference

Title
10. International Conference on Tritium Science and Technology
Acronym
TRITIUM 2013
Dates
21-25 Oct 2013
Place
Nice Acropolis (France)

Optional Information

Notes
10 refs.