ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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.
Meeting Spotlight
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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Nuclear Science and Engineering
August 2024
Nuclear Technology
July 2024
Fusion Science and Technology
Latest News
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.
Technical Session|Fundamental Thermal Hydraulics
Wednesday, August 23, 2023|10:45AM–12:25PM EDT|Columbia 2
Session Chair:
Jean-Marie Le Corre (Westinghouse)
Session Organizer:
Bao-Wen Yang (DEDQ)
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The Effect of Data Split on Correlation Errors with Respect to Independent Validation Data
10:45–11:05AM EDT
Kanghoon Kim (KEPCO Nuclear Fuel), Boemjun Jang (KEPCO Nuclear Fuel)
Paper
Investigation of the DNBR Criteria Application for NPP Safety Studies
11:05–11:25AM EDT
Attila Guba (Centre for Energy Research), Áron Hegedüs (Centre for Energy Research)
SMR Rod Bundle CHF-Characteristics and Challenges in Experimental Investigation
11:25–11:45AM EDT
Bao-Wen Yang (Delta Energy Group), Aiguo Liu (Delta Energy Group), Bin Han (Delta Energy Group)
DNB Prediction for a Subcooled Flow Boiling in a Rolling Pipe Using CFD
11:45AM–12:05PM EDT
Nam kyu Ryu (Chungnam Nat'l Univ.), Byoung jae Kim (Chungnam Nat'l Univ.)
Low Pressure Low Flow Rod Bundle CHF and its Challenges in SMR
12:05–12:25PM EDT
Bao-Wen Yang (DEQD), Bin Han (Southeast Univ.), Aiguo Liu (DEQD)
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