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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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
November 2025
Nuclear Technology
October 2025
Fusion Science and Technology
Latest News
NEA report calls for more accurate data on SNF heat decay
The OECD Nuclear Energy Agency has issued a report calling for more-detailed information on tracking the decay heat of spent nuclear fuel from light water reactors. According to the NEA, the report highlights the increasing importance of accurate decay heat estimations due to evolving fuel characteristics, including higher initial fuel enrichment, increased burn-up rates, and extended reactor cycle lengths.
The report, Summary of the NEA Assessment on Spent Nuclear Fuel Decay Heat for Light Water Reactors, summarizes the findings of a subgroup of the NEA’s Working Party on Nuclear Criticality Safety (WPNCS), which ran from January 2022 to January 2024.
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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