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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
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
Dec 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
January 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Technical Session|Severe Accidents
Tuesday, August 22, 2023|1:30–3:10PM EDT|Fairchild East/West
Session Chair:
Martina Adorni (NEA)
Alternate Chair:
Mitchell T. Farmer
Session Organizer:
David L. Luxat
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Preliminary Study on Melt Spreadability in Ex-Vessel Core Catcher Under Dry Condition
1:30–1:50PM EDT
Byung Jo Kim (KEPCO Engineering and Construction Co.), Dae Hyung Lee (KEPCO Engineering and Construction Co.), Sun Hong Yoon (KEPCO Engineering and Construction Co.)
Paper
Analysis of Corium Coolability in MCCI Conditions for Two Types of Concrete, Using ASTEC Calculations
1:50–2:10PM EDT
C. Bouillet (IRSN)
Simplified Model for One-Dimensional Ex-Vessel Corium Coolability
2:10–2:30PM EDT
Jaehoon Jung (KAERI), Seokgyu Jeong (KAERI)
Transient Cooling Investigation of a Conceptual Core Catcher Design with Embedded Cooling Tubes Using a GOTHIC 3D Model
2:30–2:50PM EDT
Zhuo Liu (China Nuclear Power Engineering Co.), Wei Li (China Nuclear Power Engineering Co.), Qiang Guo (China Nuclear Power Engineering Co.), Yidan Yuan (China Nuclear Power Engineering Co.), Ningxi Jia (China Nuclear Power Engineering Co.), Yu Jin (China Nuclear Power Engineering Co.), Weimin Ma (Royal Institute of Technology)
Presentation Video (Visible to Attendees) — pre-recorded presentation video
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