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The 2026 American Nuclear Society election is now open. Members can vote for the Society’s next vice president/president-elect as well as six board members (five U.S. directors and one non-U.S. director). Completed ballots must be submitted by 12:00 p.m. (CDT) on Wednesday, April 1, 2026.
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Hangbok Choi, John Bolin, Oscar Gutierrez, Radu Curiac, Mohammad Alavi, Matthew Virgen, Ed Chin, James Beaver, Pascal Brocheny, Geoffrey Beausoleil, Abdellatif M. Yacout, Sal Rodriguez, Michael Corradini, Daejong Kim, Steven L. Krahn, Eric Thornsbury
Nuclear Technology | Volume 211 | Number 1 | January 2025 | Pages 79-92
Research Article | doi.org/10.1080/00295450.2024.2319925
Articles are hosted by Taylor and Francis Online.
The Fast Modular Reactor (FMR) is a 100-MW(thermal) gas-cooled fast reactor being developed by General Atomics Electromagnetic System with the goal of developing a FMR for flexible and dispatchable power to the U.S. electricity market in the mid-2030s. The conceptual design aims to develop and verify simplified design features. These include an inert helium gas coolant, pellet-loaded fuel rods, installations with air cooling as ultimate heat sink, and small and passive heat removal systems. The goal is to ensure the development of a safe, maintainable, cost-effective, and distributed nuclear energy-generating station.
The baseline technologies selected to achieve this goal are a helium coolant that is an inert gas with no chemical reaction with structural components, not activated, single phase, enabling high-temperature operation and a high thermal efficiency Brayton cycle; conventional uranium dioxide (UO2) fuel, which is the most widely used and well-known fuel material, capable of high burnup (100 MWd/kg) and a long fuel life; and silicon carbide composite (SiGA®) cladding and internal structures that are chemically inert in the helium environment, exceptionally radiation tolerant, and being derisked by accident tolerant fuel technology development.
The reactor was specifically designed with passive safety features, including high-temperature in-core materials and a reactor vessel cooling system consisting of cooling panels of naturally circulating water. The passive safety of the core was confirmed for the depressurized loss-of–forced cooling accident, which showed the peak cladding temperature at ~1600°C during the transient, which is below the current design limit of 1800°C. The conceptual design of the FMR has been conducted for the reactor system, vessel system, generator and turbomachine, instrumentation and control, residual heat removal system, plant service system, and containment, as well as pre-application licensing documents.