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

Satoshi Fukada; Akio Morisaki; Akio Sagara; Takayuki Terai

doi:10.1016/j.fusengdes.2005.09.017

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

Satoshi Fukada, Akio Morisaki, Akio Sagara, Takayuki Terai

Engineering Science for Advanced energy system

Research output: Contribution to journal › Conference article › peer-review

15 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 language	English
Pages (from-to)	477-483
Number of pages	7
Journal	Fusion Engineering and Design
Volume	81 A
Issue number	1-4
DOIs	https://doi.org/10.1016/j.fusengdes.2005.09.017
Publication status	Published - Feb 2006
Event	Proceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part A - Duration: May 22 2005 → May 27 2005

All Science Journal Classification (ASJC) codes

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

Access to Document

10.1016/j.fusengdes.2005.09.017

Cite this

@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 = feb,

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",

note = "Proceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part A ; Conference date: 22-05-2005 Through 27-05-2005",

}

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

Y1 - 2006/2

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

SN - 0920-3796

VL - 81 A

SP - 477

EP - 483

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

IS - 1-4

T2 - Proceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part A

Y2 - 22 May 2005 through 27 May 2005

ER -

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

Abstract

All Science Journal Classification (ASJC) codes

Access to Document

Other files and links

Fingerprint

Cite this