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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.
A. Ibarra, R. Heidinger, P. Barabaschi, F. Mota, A. Mosnier, P. Cara, F. S. Nitti
Fusion Science and Technology | Volume 66 | Number 1 | July-August 2014 | Pages 252-259
Technical Paper | doi.org/10.13182/FST13-778
Articles are hosted by Taylor and Francis Online.
In this paper we analyze from the technical point of view the possibility of developing the IFMIF facility (International Fusion Materials Irradiation Facility) in a stepped approach from the prototypes, presently under testing in the framework of the IFMIF/EVEDA Project (IFMIF Engineering Validation and Engineering Design Activities), but with the capability to fulfill the DEMO (Demonstration reactors) needs in a first step and the fusion power plant needs in a second step. The paper is focused on the so-called DONES (DEMO Oriented Neutron Source) alternative. It is built using one of the 40 MeV IFMIF accelerators, together with a strong simplification of some of the other systems and subsystems, driven by the lower power to be handled in the DONES facility, by transferring the PIE (post-irradiation experiment) analysis to other external facilities, by reducing the remote handling activities foreseen in the facility, and by reducing the type of irradiation experiments to be performed simultaneously. A preliminary neutronic evaluation of the achievable radiation map and on the requirements for the transfer of the irradiated modules to the external facility is also presented.