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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
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
MIT’s nuclear professional courses benefit United States—and now Australia too
Some 30 nuclear engineering departments at universities across the United States graduate more than 900 students every year. These young men and women are the present and future of the domestic nuclear industry as it seeks to develop and deploy advanced nuclear energy technologies, grow its footprint on the power grid, and penetrate new markets while continuing to run the existing fleet of reactors reliably and economically.
Technical Session|Sponsored by THD
Wednesday, June 16, 2021|4:30–6:15PM EDT
Session Chair:
Elia Merzari
Alternate Chair:
Guillaume P. Mignot
Session Organizer:
Yassin A. Hassan
Staff Producer:
Jessie Vazquez (ANS)
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Preliminary Safety Analysis Results of Lead Cooled Fast Reactor: MicroURANUS under Unprotected Loss of Flow Condition
Ji Yong Kim (Ulsan Nat'l Institute of Science and Technology), In Cheol Bang (Ulsan Nat'l Institute of Science and Technology)
Paper
Numerical Study of the Heat Transfer in Randomly Packed Spheres for Fluoride Salt Cooled High-Temperature Reactors (FHRs)
Scott Wahlquist (Idaho State Univ.), Amir Ali (Idaho State Univ.)
Unified Domain Knowledge Informed Machine Learning Model for CHF Prediction
Yue Jin (MIT), Xingang Zhao (ORNL), Koroush Shirvan (MIT)
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