ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Mar 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
April 2026
Nuclear Technology
February 2026
Fusion Science and Technology
Latest News
IAEA project aims to develop polymer irradiation model
The International Atomic Energy Agency has launched a new coordinated research project (CRP) aimed at creating a database of polymer-radiation interactions in the next five years with the long-term goal of using the database to enable machine learning–based predictive models.
Radiation-induced modifications are widely applicable across a range of fields including healthcare, agriculture, and environmental applications, and exposure to radiation is a major factor when considering materials used at nuclear power plants.
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:
To access paper attachments, you must be logged in and registered for the meeting.
Register NowLog In
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)
To join the conversation, you must be logged in and registered for the meeting.