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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
Standards Program
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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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.
Workshop
Sunday, October 3, 2021|2:00–6:00PM EDT
Session Chair:
Wiliam Wieselquist (ORNL)
Alternate Chairs:
Rike Bostelmann (ORNL)
Steve Skutnik (ORNL)
Erik Walker (ORNL)
Student Producer:
Joseph Fustero (NC State Univ.)
SCALE (scale.ornl.gov) is a comprehensive modeling and simulation suite for nuclear safety analysis and design developed and maintained by Oak Ridge National Laboratory under contract with the U.S. Nuclear Regulatory Commission, U.S. Department of Energy, and the National Nuclear Security Administration to perform reactor physics, criticality safety, radiation shielding, and spent fuel characterization for nuclear facilities and transportation/storage package designs. This workshop will present recent light water reactor (LWR) and non-LWR applications using SCALE. In LWR space, this includes High Assay Low-enriched Uranium (HALEU) up to 8% enrichment, High Burnup (HBU) up to 80 GWd/MTU, and Accident Tolerant Fuel (ATF) concepts. In non-LWR space, this includes neutronics and inventory calculations for the following reactor types: Heat Pipe Reactor (HPR), Sodium Fast Reactor (SFR), Fluoride High Temperature Reactor (FHR), High Temperature Gas Reactor (HTGR), and Molten Salt Reactor (MSR). An open-source SCALE model for the HPR, HTGR, and FHR will be provided to participants, results presented, inputs/outputs reviewed, and questions answered from the participants. The instructors will use SCALE 6.3 beta16 , although the majority of the analyses may be performed with the latest release in the previous 6.2 series, 6.2.4, available from rsicc.ornl.gov. Inputs/outputs and links to slides may be found here: https://code.ornl.gov/scale/analysis/non-lwr-models-vol3
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Reference — HPR NRC+SCALE+MELCOR
Reference — HTGR NRC+SCALE+MELCOR
Reference — FHR NRC+SCALE+MELCOR
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