TY - JOUR
T1 - JUPITER-II molten salt Flibe research
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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U2 - 10.1016/j.fusengdes.2005.08.101
DO - 10.1016/j.fusengdes.2005.08.101
M3 - Conference article
AN - SCOPUS:32544435807
SN - 0920-3796
VL - 81
SP - 1439
EP - 1449
JO - Fusion Engineering and Design
JF - Fusion Engineering and Design
IS - 8-14 PART B
Y2 - 22 May 2005 through 27 May 2005
ER -