Development of Tritium Tracer Doped Liquid Fuel Target for Inertial Confinement Fusion at the Gekko XII-LFEX Facility. (18th May 2020)

• Record Type: Journal Article
• Authors: Arikawa, Yasunobu; Iwasa, Yuki; Yamanoi, Kohei; Iwano, Keisuke; Fujioka, Shinsuke; Iwamoto, Akifumi; Nakai, Mitsuo; Hatano, Yuji; Hara, Masanori; Akamaru, Satoshi; Norimatsu, Takayoshi; Kodama, Ryosuke
• Is Part Of: Fusion science and technology. Volume 76:Number 4(2020)
• Page Start: 464
• Page End: 470
• Publication Date: 2020-05-18
• Subjects: Inertial confinement fusion -- tritium-contained target -- fast ignition; Fusion reactors -- Periodicals; Nuclear fusion -- Periodicals; Fusion reactors; Nuclear fusion; Periodicals; 621.48405
• DOI: 10.1080/15361055.2020.1716458
• Languages: English
• ISSNs: 1536-1055

Abstract

Abstract: In inertial confinement fusion (ICF), a fuel target containing deuterium and tritium is used. In recent ICF experiments on the Gekko XII LFEX facility at the Institute of Laser Engineering at Osaka University (ILE-Osaka), a target comprised of a polystyrene capsule filled with D2 O liquid and a solution of X-ray tracer materials, such as copper, titanium, or chlorine, was developed. In this study, an additional T2 O doping technique by which tritium can be mixed uniformly has been developed. The T2 O is synthesized by T2 gas using a CuO oxidation catalyst. The T2 O is agglutinated by cold trap and transferred to a target cell in which a D2 O-solution-filled target is placed. Because polystyrene is slightly permeable for T2 O and D2 O, D2 O is exchanged by T2 O and completely mixed. Thus, a uniform tritium-doped ICF target with various materials can be fabricated. The T2 O synthesizing and doping system is developed and tested using H2 as a cold run. The H2 O is successfully doped to a D2 O prefilled target at approximately 50% doping. This scheme will be utilized in future fast ignition experiments at ILE-Osaka.