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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
DOE on track to deliver high-burnup SNF to Idaho by 2027
The Department of Energy said it anticipated delivering a research cask of high-burnup spent nuclear fuel from Dominion Energy’s North Anna nuclear power plant in Virginia to Idaho National Laboratory by fall 2027. The planned shipment is part of the High Burnup Dry Storage Research Project being conducted by the DOE with the Electric Power Research Institute.
As preparations continue, the DOE said it is working closely with federal agencies as well as tribal and state governments along potential transportation routes to ensure safety, transparency, and readiness every step of the way.
Watch the DOE’s latest video outlining the project here.
Bradley Heath, Colby Jensen
Nuclear Technology | Volume 206 | Number 9 | September 2020 | Pages 1436-1448
Technical Paper | doi.org/10.1080/00295450.2020.1725370
Articles are hosted by Taylor and Francis Online.
The Transient Reactor Test (TREAT) Facility is a graphite reactor capable of delivering tailored power histories to unique experiment designs. Frequently, these experiments are designed to simulate a specific reactor transient to perform detailed studies of reactor fuel behavior. The reactor core is uniquely designed to allow a limited energy release and resulting peak fuel cladding temperature such that thermal feedback mechanisms shut the reactor power transient down in a passive manner, thus maximizing the lifetime of the reactor fuel cladding. The reactor is air cooled; however, the cooling system does not serve a safety function. The air cooling is typically used for four main functions: (1) accelerate cooling of the reactor core to ambient temperature post transient operations, (2) remove activated gases from the reactor cavity, (3) perform heat balance for power calibration, and (4) maintain criticality on extended steady-state runs or shaped transients. With the restart of the reactor, these systems are now fully operational and have been exercised during the past year for the first time in more than 20 years. This paper summarizes the thermal properties of the core and the thermal-hydraulic design of the TREAT Facility and presents selected results of temperature profiles resulting from operation. Conservatively estimated maximum transient energy and steady-state power is provided.