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Antares achieves zero-power criticality at INL
Leveraging more than $140 million in private capital fundraising, over 322,000 square feet of operational manufacturing space, and multifaceted partnerships with the Departments of Energy and Defense, reactor start-up Antares has become the first company involved in the Reactor Pilot Program to achieve zero-power fueled criticality—a full month ahead of the July 4 deadline set by President Trump’s Executive Order 14301.
This milestone, announced yesterday, was achieved with the company’s Mark-0: a sodium heat-pipe-cooled, TRISO-fueled microreactor. The Mark-0 is a forerunner to the company’s flagship design, which it calls the R1. For Antares, this development represents a key validation of its reactor physics, control systems, and supply chain.
M. Subbotin, M. Rozenkevich, A. Gostev, A. Bukin, V. Khripunov, V. Kochin, S. Marunich, Yu. Pak, A. Perevezentsev, G. Sharova
Fusion Science and Technology | Volume 76 | Number 3 | April 2020 | Pages 297-303
Technical Paper | doi.org/10.1080/15361055.2020.1711851
Articles are hosted by Taylor and Francis Online.
The tokamak Ignitor project is one of the main topics of long-term scientific cooperation between the Russian Federation and the Italian Republic. The tokamak Ignitor has a super-strong magnetic field (13 T) and a powerful discharge current (11 MA for 10 s). Ohmic heating is the main mechanism for the ignition of the fusion reaction.
The location of the tokamak Ignitor on the Russian side has been proposed to be the complex Tokamak with Strong Field (TSP complex), which is located on the JSC “SRC RF TRINITI” (TRINITI) Joint Stock Company – State Research Center of Russian Federation Troitsk Institute for Innovation and Fusion Research site (Moscow, Troitsk, Russia). The TSP complex has unique engineering and physical and energy infrastructure, but it will be necessary to deeply modernize the infrastructure.
In the phase of the deuterium-tritium experiments on the tokamak Ignitor, providing a total tritium flow of 10 to 15 g/day will be required. Therefore, it is necessary to consider the development of a full-scale tritium complex with the entire set of solved tasks for the preparation and supply of the fuel mixture, the purification of the plasma exhaust products, and the separation of the isotopes.