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Tritium Inventory in Graphite

By 芦田 完 and 渡辺 国昭

Abstract

Graphite is widely used as a plasma facing component in many magnetically confined fusion devices. Before using it in D-T burning experimental devices, tritium inventory and recycling in graphite should be understood with respect to fuel balance control, safety control and tritium economy. Tritium inventory in a high temperature region (700-1000℃) was measured for graphite of various grades. The results indicate that the tritium inventory was determined by diffusion limited process. The diffusion constants of tritium for samples of graphite differed by one order of magnitude from each other. Nevertheless, tritium inventory was mainly determined from crystallite size. In addition, a first interpretation was given for the scattering of diffusion constants of tritium in graphite reported so far through the compensation effect

Publisher: 富山大学トリチウム科学センター
Year: 1989
OAI identifier: oai:toyama.repo.nii.ac.jp:00006380
Journal:

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