Mass-transport properties to estimate rates of tritium recovery from flibe blanket

Satoshi Fukada, Masabumi Nishikawa, Akio Sagara, Takayuki Terai

Research output: Contribution to journalArticle

11 Citations (Scopus)

Abstract

Rates of the recovery of tritium from a blanket of a fusion reactor with a 1 GWt power are estimated. The recovery methods are a permeation window, a Flibe-He counter-current-extraction tower and a rotational centrifugal flow system. There is high possibility in that the rate-determining step of the permeation window is tritium diffusion in Flibe. The tritium diffusion in liquid Flibe drops is also the dominant process in the counter-current-extraction tower. The determination of the tritium diffusion rate in purified or unpurified Flibe (or actual blanket environment) is a key to estimate the tritium recovery rate accurately.

Original languageEnglish
Pages (from-to)1054-1058
Number of pages5
JournalFusion Science and Technology
Volume41
Issue number3 II
Publication statusPublished - May 1 2002

    Fingerprint

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

Fukada, S., Nishikawa, M., Sagara, A., & Terai, T. (2002). Mass-transport properties to estimate rates of tritium recovery from flibe blanket. Fusion Science and Technology, 41(3 II), 1054-1058.