JUPITER-II molten salt Flibe research: An update on tritium, mobilization and redox chemistry experiments

David A. Petti; G. R. Smolik; Michael F. Simpson; John P. Sharpe; R. A. Anderl; S. Fukada; Y. Hatano; M. Hara; Y. Oya; T. Terai; D. K. Sze; S. Tanaka

doi:10.1016/j.fusengdes.2005.08.101

JUPITER-II molten salt Flibe research: An update on tritium, mobilization and redox chemistry experiments

David A. Petti^*, G. R. Smolik, Michael F. Simpson, John P. Sharpe, R. A. Anderl, S. Fukada, Y. Hatano, M. Hara, Y. Oya, T. Terai, D. K. Sze, S. Tanaka

^*この論文の責任著者

研究推進機構水素同位体科学研究センター

研究成果: ジャーナルへの寄稿 › 会議記事 › 査読

47 被引用数 (Scopus)

抄録

The second Japan/US Program on Irradiation Tests for Fusion Research (JUPITER-II) began on April 1, 2001. Part of the collaborative research centers on studies of the molten salt 2LiF₂-BeF₂ (also known as Flibe) for fusion applications. Flibe has been proposed as a self-cooled breeder in both magnetic and inertial fusion power plant designs over the last 25 years. The key feasibility issues associated with the use of Flibe are the corrosion of structural material by the molten salt, tritium behavior and control in the molten salt blanket system, and safe handling practices and releases from Flibe during an accidental spill. These issues are all being addressed under the JUPITER-II program at the Idaho National Laboratory in the Safety and Tritium Applied Research (STAR) facility. In this paper, we review the program to date in the area of tritium/deuterium behavior, Flibe mobilization under accident conditions and testing of Be as a redox agent to control corrosion. Future activities planned through the end of the collaboration are also presented.

本文言語	英語
ページ（範囲）	1439-1449
ページ数	11
ジャーナル	Fusion Engineering and Design
巻	81
号	8-14 PART B
DOI	https://doi.org/10.1016/j.fusengdes.2005.08.101
出版ステータス	出版済み - 2006/02
イベント	Proceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part B - 継続期間: 2005/05/22 → 2005/05/27

ASJC Scopus 主題領域

土木構造工学
原子力エネルギーおよび原子力工学
材料科学一般
機械工学

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10.1016/j.fusengdes.2005.08.101

引用スタイル

Petti, D. A., Smolik, G. R., Simpson, M. F., Sharpe, J. P., Anderl, R. A., Fukada, S., Hatano, Y., Hara, M., Oya, Y., Terai, T., Sze, D. K., & Tanaka, S. (2006). JUPITER-II molten salt Flibe research: An update on tritium, mobilization and redox chemistry experiments. Fusion Engineering and Design, 81(8-14 PART B), 1439-1449. https://doi.org/10.1016/j.fusengdes.2005.08.101

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title = "JUPITER-II molten salt Flibe research: An update on tritium, mobilization and redox chemistry experiments",

abstract = "The second Japan/US Program on Irradiation Tests for Fusion Research (JUPITER-II) began on April 1, 2001. Part of the collaborative research centers on studies of the molten salt 2LiF2-BeF2 (also known as Flibe) for fusion applications. Flibe has been proposed as a self-cooled breeder in both magnetic and inertial fusion power plant designs over the last 25 years. The key feasibility issues associated with the use of Flibe are the corrosion of structural material by the molten salt, tritium behavior and control in the molten salt blanket system, and safe handling practices and releases from Flibe during an accidental spill. These issues are all being addressed under the JUPITER-II program at the Idaho National Laboratory in the Safety and Tritium Applied Research (STAR) facility. In this paper, we review the program to date in the area of tritium/deuterium behavior, Flibe mobilization under accident conditions and testing of Be as a redox agent to control corrosion. Future activities planned through the end of the collaboration are also presented.",

keywords = "Flibe, JUPITER-II, Molten salt",

author = "Petti, {David A.} and Smolik, {G. R.} and Simpson, {Michael F.} and Sharpe, {John P.} and Anderl, {R. A.} and S. Fukada and Y. Hatano and M. Hara and Y. Oya and T. Terai and Sze, {D. K.} and S. Tanaka",

note = "Funding Information: The work was supported partially by U.S. Department of Energy Office of Fusion Energy Sciences, and by the Japan-US joint research program, JUPITER-II, under DOE Idaho Operations Contract DE-AC07-99ID13727. ; Proceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part B ; Conference date: 22-05-2005 Through 27-05-2005",

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doi = "10.1016/j.fusengdes.2005.08.101",

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

AU - Petti, David A.

AU - Smolik, G. R.

AU - Simpson, Michael F.

AU - Sharpe, John P.

AU - Anderl, R. A.

AU - Fukada, S.

AU - Hatano, Y.

AU - Hara, M.

AU - Oya, Y.

AU - Terai, T.

AU - Sze, D. K.

AU - Tanaka, S.

N1 - Funding Information: The work was supported partially by U.S. Department of Energy Office of Fusion Energy Sciences, and by the Japan-US joint research program, JUPITER-II, under DOE Idaho Operations Contract DE-AC07-99ID13727.

PY - 2006/2

Y1 - 2006/2

N2 - The second Japan/US Program on Irradiation Tests for Fusion Research (JUPITER-II) began on April 1, 2001. Part of the collaborative research centers on studies of the molten salt 2LiF2-BeF2 (also known as Flibe) for fusion applications. Flibe has been proposed as a self-cooled breeder in both magnetic and inertial fusion power plant designs over the last 25 years. The key feasibility issues associated with the use of Flibe are the corrosion of structural material by the molten salt, tritium behavior and control in the molten salt blanket system, and safe handling practices and releases from Flibe during an accidental spill. These issues are all being addressed under the JUPITER-II program at the Idaho National Laboratory in the Safety and Tritium Applied Research (STAR) facility. In this paper, we review the program to date in the area of tritium/deuterium behavior, Flibe mobilization under accident conditions and testing of Be as a redox agent to control corrosion. Future activities planned through the end of the collaboration are also presented.

AB - The second Japan/US Program on Irradiation Tests for Fusion Research (JUPITER-II) began on April 1, 2001. Part of the collaborative research centers on studies of the molten salt 2LiF2-BeF2 (also known as Flibe) for fusion applications. Flibe has been proposed as a self-cooled breeder in both magnetic and inertial fusion power plant designs over the last 25 years. The key feasibility issues associated with the use of Flibe are the corrosion of structural material by the molten salt, tritium behavior and control in the molten salt blanket system, and safe handling practices and releases from Flibe during an accidental spill. These issues are all being addressed under the JUPITER-II program at the Idaho National Laboratory in the Safety and Tritium Applied Research (STAR) facility. In this paper, we review the program to date in the area of tritium/deuterium behavior, Flibe mobilization under accident conditions and testing of Be as a redox agent to control corrosion. Future activities planned through the end of the collaboration are also presented.

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JUPITER-II molten salt Flibe research: An update on tritium, mobilization and redox chemistry experiments

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