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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Argonne scientists use AI to detect hidden defects in stainless steel
Imagine you’re constructing a bridge or designing an airplane, and everything appears flawless on the outside. However, microscopic flaws beneath the surface could weaken the entire structure over time.
These hidden defects can be difficult to detect with traditional inspection methods, but a new technology developed by scientists at the U.S. Department of Energy’s Argonne National Laboratory is changing that. Using artificial intelligence and advanced imaging techniques, researchers have developed a method to reveal these tiny flaws before they become critical problems.
Advances in Thermal Hydraulics (ATH 2024)
Technical Session
Wednesday, November 20, 2024|10:00–11:45AM EST|Coral A
Session Chair:
Rui Hu (ANL)
Alternate Chair:
Bart Verdonschot (NRG)
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A Numerical Test Bed on Algorithms Efficient for Advanced System Analysis Code Development
10:00–10:20AM EST
Ling Zou (ANL), Rui Hu (ANL)
Paper
Implementing a Corrosion-Oxidation Modeling Capability in SAM for Lead-Cooled Fast Reactors
10:20–10:40AM EST
Travis Mui (ANL), Thanh Hua (ANL), Ling Zou (ANL), Rui Hu (ANL), Jun Liao (Westinghouse Electric Co.)
Severe Accident Analysis of OPR-1000 Plant Using CINEMA Code
10:40–11:00AM EST
Jun-young Kang (KAERI), Donggun Son (KAERI), Jae Hyun Ham (KAERI), Yong Mann Song (KAERI), Jun Ho Bae (KAERI)
A New One-Dimensional Model for Thermal Mixing and Stratification in Reactor Applications
11:00–11:20AM EST
Eric Cervi (ANL), Ling Zou (ANL), Yeongshin Jeong (ANL), Rui Hu (ANL)
Development of A System Analysis Model to Evaluate the Conceptual Design of the Reactor Cavity Cooling System of the Horizontal Compact High Temperature Gas-Cooled Reactor (HC-HTGR)
11:20–11:40AM EST
Yeongshin Jeong (ANL), Darius Lisowski (ANL), Qiuping Lv (ANL), Rui Hu (ANL)
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