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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.
Teruya Tanaka, Hiroyuki Noto, Fuminobu Sato, Yoshimitsu Hishinuma, Hiroyuki A. Sakaue, Masahito Yoshino
Fusion Science and Technology | Volume 75 | Number 8 | November 2019 | Pages 1076-1083
Technical Paper | doi.org/10.1080/15361055.2019.1658039
Articles are hosted by Taylor and Francis Online.
To examine the impact of nuclear transmutation in K-type and N-type thermocouples on temperature measurements in a fusion reactor, thermocouples with altered compositions were fabricated, and their responses were obtained at up to 800°C. The compositions of the thermocouples were altered according to transmutation calculations simulating the 3.5-, 4.6-, and 7-year use at the first wall and 40-year use at the front surface of the radiation shield. Comparison of the responses with commercial thermocouples at 800°C showed that the K-type and N-type thermocouples with altered composition simulating the 7-year use at the first wall indicate 20% to 25% lower temperatures. In this condition, the weight ratio of additive powders for simulation of transmuted elements was ~3%. The differences of responses between the commercial thermocouples and thermocouples simulating transmutation are dependent on the weight ratio of the additive powders. The present data could be used for estimation of response degradation of thermocouples used for long-term operation in a fusion reactor.