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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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
Feb 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
February 2025
Nuclear Technology
Fusion Science and Technology
Latest News
NRC issues Palisades’ draft environmental review, seeks public comment
The Nuclear Regulatory Commission is asking for public comments until March 3 on its environmental assessment (EA) and draft finding of no significant impact at Michigan’s Palisades nuclear power plant, where Holtec hopes to restart operations by the end of 2025.
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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