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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!
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Nuclear Science and Engineering
May 2025
Nuclear Technology
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Latest News
Los Alamos researchers test TRISO transportation
Los Alamos National Laboratory recently performed a series of customized criticality experiments to obtain data that will support the transportation of HALEU TRISO fuel, the Department of Energy announced April 21.
Advances in Thermal Hydraulics (ATH 2022)
Technical Session
Tuesday, June 14, 2022|1:00–2:45PM PDT|Redondo
Session Chair:
Subash Sharma (UMass Lowell)
Alternate Chair:
Trevor Howard (Oregon State)
Session Organizers:
Matthew D. Zimmer (Naval Nuclear Lab)
Xu Wu (NCSU)
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CFD Analysis of the Sodium-Water Reaction in the Minichannel of PCSG Designed for SFR
Taewoo Kim (Korea Univ. Science and Technology), Hyun-Sik Park (KAERI), Sang Ji Kim (KAERI)
Paper
A Multiphysics Framework Using High Resolution DNS to Optimize Conditions for Plasma Formation
Naveen Pillai (NCSU), Nicholas L. Sponsel (NCSU), Katharina Stapelmann (NCSU), Igor A. Bolotnov (NCSU)
A Conceptual Study of Air Curtain on the Reactor Vessel Auxiliary Cooling System
Jaejin Choi (KAIST), Yong Hoon Jeong (KAIST)
Development of Integrated Safety Analysis Code with Capability of Detailed Simulation for Multiple Fuel Rods
Yunseok Lee (Incheon National Univ.), Jaeseung Suh (SenTech Co.), Taewan Kim (Incheon National Univ.)
LES of Natural Convection Along the Vertical Wall Applied for the Scale of Small Modular Reactor ( Ra*≈10^19)
Songzhi Yang (CEA), Ulrich Bieder (CEA)
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