Evaluation and improvement of properties of hydride shielding materials for a fusion reactor

2015 Fiscal Year Final Research Report

• Project/Area Number: 25289344
• 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: National Institute for Fusion Science
• Principal Investigator: Tanaka Teruya 核融合科学研究所, ヘリカル研究部, 准教授 (30353444)
• Co-Investigator(Kenkyū-buntansha): SAGARA Akio 核融合科学研究所, ヘリカル研究部, 教授 (20187058) ; HISHINUMA Yoshimitsu 核融合科学研究所, ヘリカル研究部, 准教授 (00322529) ; KONDO Masatoshi 東京工業大学, 原子炉工学研究所, 助教 (70435519) ; YOSHINO Masahito 名古屋大学, 工学研究科, 助教 (10397466) ; SAKAUE Hiroyuki 核融合科学研究所, ヘリカル研究部, 助教 (40250112) ; MUTA Hiroaki 大阪大学, 工学研究科, 助教 (60362670) ; TAMURA Hitoshi 核融合科学研究所, ヘリカル研究部, 准教授 (20236756)
• Project Period (FY): 2013-04-01 – 2016-03-31
• Keywords: 水素化物 / 中性子遮蔽 / 粉末プレス / 重量密度 / 熱伝導 / ZrH2 / TiH2

Outline of Final Research Achievements

Test fabrication of hydride blocks using commercially available ZrH2 and TiH2 powders were performed by the cold isostatic press (CIP) process (typical dimensions: ~2.5x2.5x2.5cm3, 398MPa). The obtained densities were ~80% and 85% compared with the theoretical densities, respectively. The effective density of the hydride component increased to ~95 % by using a Cu-coated TiH2 powder and die pressing. This could be a potential method for the densification of the blocks. Thermal desorption spectroscopy (TDS) data of the hydride powders were obtained in high vacuum, Ar, He+H2 and air environment to investigate the hydrogen retention properties under accidental conditions. Effective positions of hydride blocks in a fusion reactor, form of use and atmosphere control were proposed based on the results. The hydrogen release temperature of the ZrH2 material was significantly decreased due to oxidation in air.

Free Research Field

核融合中性子工学・機能材料