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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
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
Nov 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Japanese researchers test detection devices at West Valley
Two research scientists from Japan’s Kyoto University and Kochi University of Technology visited the West Valley Demonstration Project in western New York state earlier this fall to test their novel radiation detectors, the Department of Energy’s Office of Environmental Management announced on November 19.
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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