New development of research aimed at the realization of a nuclear fusion reactor. Grant in Aid for Scienrific Research for Priority Areas(2007 tp 2011) Science and Technolgy for Fusion Reactor
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Tritium Science and Technolgy for Fusion Reactor
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Research Projects

Research item A "Buildup and Removal of Tritium"

Project Name
Experimental studies on in-vessel tritium inventory in complicated environment of fusion reactors. PDF

Project leader
Yoshio Ueda
(Professor of School/ Graduate School of Engineering, Osaka University)

The purpose of this project is to understand tritium behavior in wall materials and deposition layers through basic experiments in small devices and large magnetic confinement devices. Accurate estimation of in-vessel tritium inventory in ITER and DEMO reactors will be realized in cooperation with the simulation research group(A02). Final goal is to achieve control methoos to keep in-vessel tririum inventory below the safety limit.

Project Name
Theory and code development for evaluation of tritium retention and exhaust in fusion reactor. PDF

Project leader
Kaoru Ohya
(Professor of Institute of Technology and Science, The University of Tokushima)

An integrated computer simulation code, which is based on theories of tritium plasma-wall interactions, is developed in order to evaluate accurately tritium retention and exhaust in fusion reactors.

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Research item B "Explaining the behavior of tritium in Nuclear reactor blankets"

Project Name
Study of clarifying tritium transfer in materials of fusion reactor blanket and developing new processes for tritium recovery from fusion reactor system. PDF

Project leader
Satoshi Fukada
(Professor of Interdisciplinary Graduate School of Engineering Sciences, Kyushu University)

Based on our experiment of tritium release from solid or liquid blanket systems after neutron irradiation and our development of numerical simulation programs to analyze tritium migration in blanket materials, we will new design tritium breeding blankets and tritium recovery systems that can satisfy the two conditions of safety and economics on tritium and fusion reactor in this scientific research in priority area.

Project Name
The behavior of tritium in high temperature melted blanket liquid; invisible leak prevention and recovery. PDF

Project leader
Takayuki Terai
(Professor of Graduate School of Engineering, University of Tokyo)

Explain the generation, dissolution and spread of tritium in liquid blankets and its interaction with facing materials. At the same time research an innovative tritium recovery process that can demonstrate to the fullest, the benefits of a self-cooling type blanket.

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Research Item C Safe containment of tritium in nuclear fusion reactors and

Project Name
R&D on effect of chemical behaviors of high level tritium in organic compounds and water on tritium confinement. PDF

Project leader
Toshihiko Yamanishi
(Japan Atomic Energy Agency)

In this research group, two R&D studies are discussed and arranged: R&D on effect of chemical behaviors of high level tritium in organic compounds and water on tritium confinement; and Study on tritium permeation and decontamination. The design of the fusion fuel loop of ITER has been completed based on the previous R&D results for tritium and the operation experience of large amount of tritium in the world. This means that the database for the tritium behavior as a hydrogen isotope has been studied in detail. However, the behavior of tritium water and tritium organic compounds has not yet been well studied. From this viewpoint, the above two R&D studies have been started from this year for 5 years. In the two R&D studies, there are some common subjects. The principal objective of the present research group is to discuss and to arrange the results of the two R&D studies. Through these activities of this research group, the progress of the two R&D studies are expected to be enhanced each other.

Project Name
Tritium permeation, contamination and decontamination. PDF

Project leader
Yuji Hatano
(Professor of Hydrogen Isotope Research Center, University of Toyama)

This group investigates the mechanism of tritium release from highly contaminated materials by measuring release rate, chemical form and surface state of materials to control the tritium emission to work areas in fusion plants and to the environment.

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