Estimation of tritium permeation rate to cooling water in fusion DEMO condition

Kazunari Katayama, Youji Someya, Kenji Tobita, Hirofumi Nakamura, Hisashi Tanigawa, Makoto Nakamura, Nobuyuki Asakura, Kazuo Hoshino, Takumi Chikada, Yuji Hatano, Satoshi Fukada

Research output: Contribution to journalArticle

7 Citations (Scopus)

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 twocomponent 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.

Original languageEnglish
Pages (from-to)261-267
Number of pages7
JournalFusion Science and Technology
Volume71
Issue number3
DOIs
Publication statusPublished - Apr 1 2017

Fingerprint

liquid cooling
Tritium
Cooling water
tritium
Permeation
Fusion reactions
fusion
blankets
Tungsten
fusion reactors
Fusion reactors
Hydrogen
safety
tungsten
Gases
Plasmas
Water
evaluation
hydrogen
gases

All Science Journal Classification (ASJC) codes

  • Civil and Structural Engineering
  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Mechanical Engineering

Cite this

Katayama, K., Someya, Y., Tobita, K., Nakamura, H., Tanigawa, H., Nakamura, M., ... Fukada, S. (2017). Estimation of tritium permeation rate to cooling water in fusion DEMO condition. Fusion Science and Technology, 71(3), 261-267. https://doi.org/10.1080/15361055.2017.1288423

Estimation of tritium permeation rate to cooling water in fusion DEMO condition. / Katayama, Kazunari; Someya, Youji; Tobita, Kenji; Nakamura, Hirofumi; Tanigawa, Hisashi; Nakamura, Makoto; Asakura, Nobuyuki; Hoshino, Kazuo; Chikada, Takumi; Hatano, Yuji; Fukada, Satoshi.

In: Fusion Science and Technology, Vol. 71, No. 3, 01.04.2017, p. 261-267.

Research output: Contribution to journalArticle

Katayama, K, Someya, Y, Tobita, K, Nakamura, H, Tanigawa, H, Nakamura, M, Asakura, N, Hoshino, K, Chikada, T, Hatano, Y & Fukada, S 2017, 'Estimation of tritium permeation rate to cooling water in fusion DEMO condition', Fusion Science and Technology, vol. 71, no. 3, pp. 261-267. https://doi.org/10.1080/15361055.2017.1288423
Katayama, Kazunari ; Someya, Youji ; Tobita, Kenji ; Nakamura, Hirofumi ; Tanigawa, Hisashi ; Nakamura, Makoto ; Asakura, Nobuyuki ; Hoshino, Kazuo ; Chikada, Takumi ; Hatano, Yuji ; Fukada, Satoshi. / Estimation of tritium permeation rate to cooling water in fusion DEMO condition. In: Fusion Science and Technology. 2017 ; Vol. 71, No. 3. pp. 261-267.
@article{12ea99cd05f24e31bfad056a86533207,
title = "Estimation of tritium permeation rate to cooling water in fusion DEMO condition",
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 twocomponent 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.",
author = "Kazunari Katayama and Youji Someya and Kenji Tobita and Hirofumi Nakamura and Hisashi Tanigawa and Makoto Nakamura and Nobuyuki Asakura and Kazuo Hoshino and Takumi Chikada and Yuji Hatano and Satoshi Fukada",
year = "2017",
month = "4",
day = "1",
doi = "10.1080/15361055.2017.1288423",
language = "English",
volume = "71",
pages = "261--267",
journal = "Fusion Science and Technology",
issn = "1536-1055",
publisher = "American Nuclear Society",
number = "3",

}

TY - JOUR

T1 - Estimation of tritium permeation rate to cooling water in fusion DEMO condition

AU - Katayama, Kazunari

AU - Someya, Youji

AU - Tobita, Kenji

AU - Nakamura, Hirofumi

AU - Tanigawa, Hisashi

AU - Nakamura, Makoto

AU - Asakura, Nobuyuki

AU - Hoshino, Kazuo

AU - Chikada, Takumi

AU - Hatano, Yuji

AU - Fukada, Satoshi

PY - 2017/4/1

Y1 - 2017/4/1

N2 - 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 twocomponent 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.

AB - 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 twocomponent 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.

UR - http://www.scopus.com/inward/record.url?scp=85036471065&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=85036471065&partnerID=8YFLogxK

U2 - 10.1080/15361055.2017.1288423

DO - 10.1080/15361055.2017.1288423

M3 - Article

AN - SCOPUS:85036471065

VL - 71

SP - 261

EP - 267

JO - Fusion Science and Technology

JF - Fusion Science and Technology

SN - 1536-1055

IS - 3

ER -