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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
May 2025
Jan 2025
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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
Latest News
NWMO chooses vendors for Canadian repository
Canada’s Nuclear Waste Management Organization has selected five companies it is to work with to design and plan the organization’s proposed deep geologic repository for spent nuclear fuel. As the owner of the project, the NWMO will be working with WSP Canada, Peter Kiewit Sons (Kiewit), Hatch Ltd., Thyssen Mining Construction of Canada, and Kinectrics.
Advances in Thermal Hydraulics (ATH 2024)
Technical Session
Wednesday, November 20, 2024|3:15–5:00PM EST|Coral A
Session Chair:
Trevor Howard (OSU)
Alternate Chair:
Victor Petrov (PSI)
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Multi-physics Simulation of a Reference Fluoride-Salt-Cooled High-Temperature Reactor with Coupled SAM/Griffin
3:15–3:35PM EST
Gang Yang (ANL), Ling Zou (ANL), Rui Hu (ANL), Zhiee Jhia Ooi (ANL), Travis Mui (ANL), Javier Ortensi (INL), Joshua Hanophy (INL)
Paper
Application of Real-Time Hybrid Simulation to Nuclear Thermal Hydraulics Testing
3:35–3:55PM EST
Austin M. Warren (Oregon State), Trevor K. Howard (Oregon State)
Dry-Out Limit Investigation and Methodology for Determining the Optimal Charging Amount of Sodium Heat Pipes
3:55–4:15PM EST
Dong Hun Lee (Ulsan Nat'l Institute Science and Technology), In Cheol Bang (Ulsan Nat'l Institute Science and Technology)
Preliminary Pin-Wise Multi-Physics Simulation Using CUPID Subchannel Module Coupled with Neutron Kinetics Code and Fuel Performance Code
4:15–4:35PM EST
Yeonghun Lee (Seoul Nat'l Univ.), Kyuseok Sim (Seoul Nat'l Univ.), Youho Lee (Seoul Nat'l Univ.), Jae Ryong Lee (KAERI), Hyoung Kyu Cho (Seoul Nat'l Univ.)
Preliminary Test of the Single Heat Pipe Experimental Facility with Azimuthally Asymmetric Condition
4:35–4:55PM EST
San Lee (Seoul Nat'l Univ.), Myeong Jin Jeong (Seoul Nat'l Univ.), Ye Sung Kim (Seoul Nat'l Univ.), Hyeong Kyu Cho (Seoul Nat'l Univ.)
Design and Evaluation of a Sodium Loop Heat Pipe
4:55–5:05PM EST
Hyewon Kim (Gyeongsang Nat'l Univ.), Hyeonmin Choi (Gyeongsang Nat'l Univ.), Byung Ha Park (KAERI), Hyungmo Kim (Gyeongsang Nat'l Univ.)
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