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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
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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