Control of tritium in FFHR-2 self-cooled Flibe blanket

Satoshi Fukada, Akio Morisaki, Akio Sagara, Takayuki Terai

Research output: Contribution to journalConference article

14 Citations (Scopus)

Abstract

The application of Flibe (2LiF + BeF2 mixed molten salt) to a blanket material of force-free helical reactor (FFHR-2) was discussed based on our recent experiments on redox control of Flibe by Be and on hydrogen permeation through Flinak (0.465LiF + 0.115NaF + 0.42 KF mixed molten salt) as a fluid simulant of Flibe. The two experimental works were carried out under the collaboration work of JUPITER-II. To maintain Flibe in the blanket loop under reduction condition is a key issue to transform TF to T2 with a fast reaction rate. In order to achieve that, proper rates of Be dissolution and reduction reaction of TF to T2 in Flibe have to be established in the self-cooled blanket. The overall material balance of tritium in the FFHR-2 system was discussed in terms of the tritium permeation through Flibe and the tritium recovery rate.

Original languageEnglish
Pages (from-to)477-483
Number of pages7
JournalFusion Engineering and Design
Volume81 A
Issue number1-4
DOIs
Publication statusPublished - Feb 1 2006
EventProceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part A -
Duration: May 22 2005May 27 2005

Fingerprint

Tritium
Permeation
Molten materials
Salts
Reaction rates
Hydrogen
Dissolution
Recovery
Fluids
Experiments

All Science Journal Classification (ASJC) codes

  • Energy Engineering and Power Technology
  • Nuclear Energy and Engineering
  • Civil and Structural Engineering
  • Mechanical Engineering

Cite this

Control of tritium in FFHR-2 self-cooled Flibe blanket. / Fukada, Satoshi; Morisaki, Akio; Sagara, Akio; Terai, Takayuki.

In: Fusion Engineering and Design, Vol. 81 A, No. 1-4, 01.02.2006, p. 477-483.

Research output: Contribution to journalConference article

Fukada, S, Morisaki, A, Sagara, A & Terai, T 2006, 'Control of tritium in FFHR-2 self-cooled Flibe blanket', Fusion Engineering and Design, vol. 81 A, no. 1-4, pp. 477-483. https://doi.org/10.1016/j.fusengdes.2005.09.017
Fukada, Satoshi ; Morisaki, Akio ; Sagara, Akio ; Terai, Takayuki. / Control of tritium in FFHR-2 self-cooled Flibe blanket. In: Fusion Engineering and Design. 2006 ; Vol. 81 A, No. 1-4. pp. 477-483.
@article{bf20cfab99b04f9a9843d94ad5f6d9a3,
title = "Control of tritium in FFHR-2 self-cooled Flibe blanket",
abstract = "The application of Flibe (2LiF + BeF2 mixed molten salt) to a blanket material of force-free helical reactor (FFHR-2) was discussed based on our recent experiments on redox control of Flibe by Be and on hydrogen permeation through Flinak (0.465LiF + 0.115NaF + 0.42 KF mixed molten salt) as a fluid simulant of Flibe. The two experimental works were carried out under the collaboration work of JUPITER-II. To maintain Flibe in the blanket loop under reduction condition is a key issue to transform TF to T2 with a fast reaction rate. In order to achieve that, proper rates of Be dissolution and reduction reaction of TF to T2 in Flibe have to be established in the self-cooled blanket. The overall material balance of tritium in the FFHR-2 system was discussed in terms of the tritium permeation through Flibe and the tritium recovery rate.",
author = "Satoshi Fukada and Akio Morisaki and Akio Sagara and Takayuki Terai",
year = "2006",
month = "2",
day = "1",
doi = "10.1016/j.fusengdes.2005.09.017",
language = "English",
volume = "81 A",
pages = "477--483",
journal = "Fusion Engineering and Design",
issn = "0920-3796",
publisher = "Elsevier BV",
number = "1-4",

}

TY - JOUR

T1 - Control of tritium in FFHR-2 self-cooled Flibe blanket

AU - Fukada, Satoshi

AU - Morisaki, Akio

AU - Sagara, Akio

AU - Terai, Takayuki

PY - 2006/2/1

Y1 - 2006/2/1

N2 - The application of Flibe (2LiF + BeF2 mixed molten salt) to a blanket material of force-free helical reactor (FFHR-2) was discussed based on our recent experiments on redox control of Flibe by Be and on hydrogen permeation through Flinak (0.465LiF + 0.115NaF + 0.42 KF mixed molten salt) as a fluid simulant of Flibe. The two experimental works were carried out under the collaboration work of JUPITER-II. To maintain Flibe in the blanket loop under reduction condition is a key issue to transform TF to T2 with a fast reaction rate. In order to achieve that, proper rates of Be dissolution and reduction reaction of TF to T2 in Flibe have to be established in the self-cooled blanket. The overall material balance of tritium in the FFHR-2 system was discussed in terms of the tritium permeation through Flibe and the tritium recovery rate.

AB - The application of Flibe (2LiF + BeF2 mixed molten salt) to a blanket material of force-free helical reactor (FFHR-2) was discussed based on our recent experiments on redox control of Flibe by Be and on hydrogen permeation through Flinak (0.465LiF + 0.115NaF + 0.42 KF mixed molten salt) as a fluid simulant of Flibe. The two experimental works were carried out under the collaboration work of JUPITER-II. To maintain Flibe in the blanket loop under reduction condition is a key issue to transform TF to T2 with a fast reaction rate. In order to achieve that, proper rates of Be dissolution and reduction reaction of TF to T2 in Flibe have to be established in the self-cooled blanket. The overall material balance of tritium in the FFHR-2 system was discussed in terms of the tritium permeation through Flibe and the tritium recovery rate.

UR - http://www.scopus.com/inward/record.url?scp=31844435697&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=31844435697&partnerID=8YFLogxK

U2 - 10.1016/j.fusengdes.2005.09.017

DO - 10.1016/j.fusengdes.2005.09.017

M3 - Conference article

AN - SCOPUS:31844435697

VL - 81 A

SP - 477

EP - 483

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

SN - 0920-3796

IS - 1-4

ER -