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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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
Jun 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
July 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
2024 International Congress on Advances in Nuclear Power Plants (ICAPP)
Technical Session|Thermal Hydraulics Analysis and Testing
Wednesday, June 19, 2024|10:00–11:45AM PDT|Palm H
Session Chair:
Ketan Ajay (Purdue Univ.)
Alternate Chair:
Alex Grannan (ANL)
Session Organizers:
Hiroyuki Yoshida (Japan Atomic Energy Agency)
Mauricio E. Tano (INL)
Caleb S. Brooks (Univ. Illinois, Urbana-Champaign)
Track Organizers:
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Preliminary Analysis on Thermal-Hydraulic Behavior of PBR Cores Using DEM-CFD Coupled Method
10:00–10:20AM PDT
Joong Young Seo (Seoul Nat'l Univ.), Young Beom Jo (Seoul Nat'l Univ.), Sung Joon Kwon (Seoul Nat'l Univ.), Eung Soo Kim (Seoul Nat'l Univ.)
Paper
Preliminary Multi-GPU Simulation on IVR-ERVC by Coupling Smoothed Particle Hydrodynamics and System Code
10:20–10:40AM PDT
Yelyn Ahn (Seoul Nat'l Univ.), Tae Soo Choi (Korea Institute of Nuclear Safety), So-Hyun Park (KAERI), Eung Soo Kim (Seoul Nat'l Univ.)
Safety Analysis and Design Specifications of MIT's Sodium Graphite Micro-Reactor
10:40–11:00AM PDT
N. Kallieros (ETHZ Swiss Federal Institute of Technology), G. Park (MIT), J. Buongiorno (MIT), K. Shirvan (MIT)
Presentation Slides (Visible to Attendees)
Comparative Study of Critical Heat Flux Prediction Using Deep Learning Models (Convolutional Neural Networks versus Deep Neural Networks)
11:00–11:20AM PDT
Messaoud Djeddou (Mohamed Khider Univ.), Ibrahim A. Hammed (Norwegian Univ. Science and Technology), Xingang Zhao (ORNL), Jehad Al Dallal (Gulf Univ. Science and Technology)
Inverse Problem Approach for Estimating Operating Conditions and Uncertainty Quantification in Actual Forced Convection System
11:20–11:40AM PDT
Haeseong Kim (MIT), Sacit Cetiner (INL), Matteo Bucci (MIT)
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