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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
May 2025
Fusion Science and Technology
Latest News
Two updated standards on criticality safety published
The American National Standards Institute (ANSI) recently approved two new American Nuclear Society standards covering different aspects of nuclear criticality safety (NCS).
Advances in Thermal Hydraulics (ATH 2022)
Technical Session
Tuesday, June 14, 2022|3:15–5:00PM PDT|Palos Verdes A/B
Session Chair:
Lander Ibarra (ANL)
Alternate Chair:
Milos Atz (ANL)
Session Organizer:
W. David Pointer
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MELCOR Validation Study on Sodium Pool Fire Model with Comparison to SPHINCS
David L.Y. Louie (Sandia), Mitsuhiro Aoyagi (Japan Atomic Energy Agency)
Paper
DASSH: An Open-Source, Full-Core Subchannel Code for Fast Reactor Design and Analysis
Milos Atz (ANL), Florent Heidet (ANL)
Study on Hydraulic Characteristics in KAERI 61-PIN Wire-Wrapped Fuel Assembly Using STAR-CCM+ and ANSYS CFX
Gi-Uk Choi (Gachon Univer.), Jonggan Hong (KAERI), Yo-Han Jung (KAERI), Jae-Ho Jeong (Gachon Univer.)
Prediction of Pressure Drop in Wire-Wrapped Fuel Assemblies with Blocked Channels Using Large Eddy Simulation
D.R. Shaver (ANL), E. Merzari (ANL), L. Brockmeyer (ANL), D. Dai (ANL)
Validation of Thermal-Hydraulic Data Verification in a 37-Pin Fuel Assembly of PLANDTL Facility Using STAR-CCM+
Gi-Uk Choi (Gachon Univer.), Jae-Ho Jeong (Gachon Univer.)
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