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Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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Duke Energy submits an ESP application to the NRC
Following up on an October announcement on plans to invest more heavily in nuclear power, Duke Energy closed out 2025 by submitting an early site permit application to the Nuclear Regulatory Commission. This ESP application is for a site near the Belews Creek Steam Station, a coal and natural gas plant in Stokes County, N.C., where Duke has been pursuing a new nuclear project for two years.
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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