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Hash Hashemianpresident@ans.org
From kindergarten classrooms to national security facilities, each event I attended during the opening weeks of the new year underscored one truth: The future of nuclear energy depends on the people we inspire, educate, and empower today.
I had a busy start to 2026, first speaking at the Nashville Energy and Mining Summit alongside Tennessee Electric Cooperative Association senior vice president Justin Maierhofer to explore the necessary synergies among policy, academic coursework, research, and industry expertise in accelerating American nuclear innovation. Drawing on experiences in high-level government relations and public affairs and decades of work in nuclear instrumentation advancements, we discussed Tennessee’s nuclear renaissance, workforce development, and policy frameworks that support emerging energy demands.
Yao Xiao, Lin-Wen Hu, Charles Forsberg, Suizheng Qiu, Guanghui Su, Kun Chen, Naxiu Wang
Nuclear Technology | Volume 187 | Number 3 | September 2014 | Pages 221-234
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-93
Articles are hosted by Taylor and Francis Online.
The fluoride salt–cooled high-temperature reactor (FHR) is an advanced reactor concept, which uses high-temperature TRISO fuel with a low-pressure liquid salt coolant. The design of a fluoride salt–cooled high-temperature test reactor (FHTR) is a key step in the development of the FHR technology and is currently in progress in both China and the United States. An FHTR based on a pebble bed core design with coolant temperature 600°C to 700°C is being planned for construction by the Chinese Academy of Sciences’ Thorium Molten Salt Reactor Research Center, Shanghai Institute of Applied Physics (SINAP). This paper provides a preliminary thermal-hydraulic licensing analysis of an FHTR using SINAP’s pebble core design as a reference case. The operation limits based on criteria outlined in U.S. regulatory guidelines are evaluated. Limiting safety system settings (LSSSs) considering uncertainties for forced convection and natural convection are obtained. The LSSS power and coolant outlet temperature, respectively, are 24.83 MW and 720°C for forced convection and 1.19 MW and 720°C for natural convection. The maximum temperature for the structural materials of 730°C is the most limiting constraint of the FHTR design.