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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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NRC engineers share their expertise at the University of Puerto Rico
Robert Roche-Rivera and Marcos Rolón-Acevedo are licensed professional engineers who work at the U.S. Nuclear Regulatory Commission. They are also alumni of the University of Puerto Rico–Mayagüez (UPRM) and have been sharing their knowledge and experience with students at their alma mater since last year, serving as adjunct professors in the university’s Department of Mechanical Engineering. During the 2023–2024 school year, they each taught two courses: Fundamentals of Nuclear Science and Engineering, and Nuclear Power Plant Engineering.
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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