Studies on tritium retention in surface deposition layers of plasma-facing materials

2015 Fiscal Year Final Research Report

• Project/Area Number: 25289335
• Research Category: Grant-in-Aid for Scientific Research (B)
• Allocation Type: Partial Multi-year Fund
• Section: 一般
• Research Field: Nuclear fusion studies
• Research Institution: University of Toyama
• Principal Investigator: MATSUYAMA MASAO 富山大学, 研究推進機構水素同位体科学研究センター, その他 客員教授 (90135004)
• Project Period (FY): 2013-04-01 – 2016-03-31
• Keywords: トリチウム / 保持量 / 非破壊測定 / 新規ＢＩＸＳ / 核融合炉材料

Outline of Final Research Achievements

In this study, to contribute the consideration of safety measures in maintenance work and fuel control in a fusion reactor, the advanced beta-ray-induced X-ray spectrometry (Advanced-BIXS), which is able to evaluate nondestructively tritium retention in a material in vacuum, was established and its applicability has been investigated. Purpose of the present study was to establish the Advanced-BIXS and basic database on trapping and release behavior of tritium by using it. The applicability and availability of the Advanced-BIXS was examined by measuring tritium-containing samples without air exposure during a cycle of vacuum heating, tritium exposure and measurements of an X-ray spectrum emitted from a sample.

Free Research Field

核融合工学