ウエダ　ヨシオ   Ueda Yoshio   上田　良夫    所属   追手門学院大学  理工学部 電気電子工学科    職種   教授
言語種別	英語
発行・発表の年月	2003/03
形態種別	論文
査読	査読あり
標題	PSI issues at plasma facing surfaces of blankets in fusion reactors
執筆形態	共著・編著（代表編著を除く）
掲載誌名	JOURNAL OF NUCLEAR MATERIALS
掲載区分	国外
出版社・発行元	ELSEVIER SCIENCE BV
巻・号・頁	313,pp.32-41
著者・共著者	Y Ueda,K Tobita,Y Katoh
概要	Important PSI issues for the first wall of blankets in fusion reactors are reviewed. Present understandings and remaining issues for particle loads (fast neutral, thermal ions, and energetic alpha particle ripple losses), and evaluation of low-activation structural materials (RAF, V-alloys, and SiCf/SiC) and tungsten as first-wall armor (including the effect on tritium breeding ratio of blankets) are explained. If the characteristics of particle load to the first-wall evaluated for ITER-FEAT is similar to DEMO and future reactors, erosion rates of the blanket first-wall made by low-activation materials are not acceptable considering their thickness. For this case, armor materials such as W or some protection methods such as in-situ coatings of low Z materials could be needed.
DOI	10.1016/S0022-3115(02)01329-6
ISSN	0022-3115