Estimation of Tritium Permeation Rate to Cooling Water in Fusion DEMO Condition. (3rd April 2017)

• Record Type: Journal Article
• Authors: Katayama, Kazunari; Someya, Youji; Tobita, Kenji; Nakamura, Hirofumi; Tanigawa, Hisashi; Nakamura, Makoto; Asakura, Nobuyuki; Hoshino, Kazuo; Chikada, Takumi; Hatano, Yuji; Fukada, Satoshi
• Is Part Of: Fusion science and technology. Volume 71:Number 3(2017)
• Page Start: 261
• Page End: 267
• Publication Date: 2017-04-03
• Subjects: Tritium -- permeation -- blanket -- divertor -- DEMO; Fusion reactors -- Periodicals; Nuclear fusion -- Periodicals; Fusion reactors; Nuclear fusion; Periodicals; 621.48405
• DOI: 10.1080/15361055.2017.1288423
• Languages: English
• ISSNs: 1536-1055

Abstract

Abstract: The approximate estimation of tritium permeation rate under the acceptable assumption from a safety point of view is surely useful to progress the design activities for a fusion DEMO reactor. Tritium permeation rates in the blanket and the divertor were estimated by the simplified evaluation model under the recent DEMO conditions in the water-cooled blanket with solid breeder as a first step. Plasma driven permeation rates in tungsten wall were calculated by applying Doyle & Brice model and gas driven permeation rates in F82H were calculated for hydrogen-tritium two-component system. In the representative recent DEMO condition, the following tritium permeation\ rates were obtained, 1.8 g/day in the blanket first wall, 2.3 g/day in the blanket tritium breeding region and 1.6 g/day in the divertor. Total tritium permeation rate into the cooling water was estimated to be 5.7 g/day.