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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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
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!
Latest Magazine Issues
Dec 2024
Jul 2024
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Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
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About Studsvik Scandpower
Studsvik Scandpower (SSP) is the leading global provider of vendor-independent, state-of-the-art nuclear fuel management software and world-class engineering services. SSP offers a full suite of software product offerings, training, and engineering services, to support operating utilities, fuel vendors, safety authorities, and research organizations around the world.
Advances in Thermal Hydraulics (ATH 2022)
Technical Session
Wednesday, June 15, 2022|3:15–5:00PM PDT|Manhattan
Session Chair:
Trevor Kent Howard
Alternate Chair:
Robert K. Salko
Session Organizer:
W. David Pointer
To access paper attachments, you must be logged in and registered for the meeting.
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Uncertainty Quantification in High-Low Dynamic System Coupling Using RAVEN and TRANSFORM
W.C. Williams (ORNL), V. Kumar (ORNL), W. Gurecky (ORNL), D. de Wet (ORNL)
Paper
Validation of the Coupled CUPID/MERCURY Code using Thermo-Mechanics and Thermal-Hydraulics Coupled Test Data from ICARUS
Hyun-Sik Park (KAERI), Jong-Rok Kim (KAERI), Seung-Jun Lee (KAERI), Hyo-Chan Kim (KAERI), Sang-Ki Moon (KAERI), Han-Young Yoon (KAERI)
Coupled Simulation of Reactor Pressure Vessel (RPV) Subjected to Pressurized Thermal Shock (PTS) Using Cardinal
Yiqi Yu (ANL), April Novak (ANL), Dillon Shaver (ANL), Elia Merzari (Penn State)
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