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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
Wednesday, June 15, 2022|10:15AM–12:00PM PDT|San Simeon B
Session Chair:
Bao-Wen Yang
Alternate Chair:
Jun Liao
Session Organizer:
W. David Pointer
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Realistic Loss-of-Coolant Accident Analysis of a Boiling Water Reactor for Licensing Base Revision
J. Hagaman (GE Hitachi Nuclear Energy), K. Muftuoglu (GE Hitachi Nuclear Energy), S. Lafountain (GE Hitachi Nuclear Energy), B. Sarikaya (GE Hitachi Nuclear Energy), P. Sharpe (GE Hitachi Nuclear Energy)
Paper
Analysis of Flow Instability Onset in a BWR Rod Bundle Geometry
P. Hurley (Virginia Tech), Y. Liu (Virginia Tech), J.P. Duarte (Virginia Tech), M. Corradini (Univ. Wisconsin, Madison), T. Kozlowski (Univ. Illinois, Urbana-Champaign)
Design Study of CRUD Thermal Properties Characterization Facility DISNY Under Pressurized Water Reactor Normal Operating Condition
Ji Yong Kim (Ulsan Nat'l Institute of Science and Technology), Hyeon Ji Kim (Ulsan Nat'l Institute of Science and Technology), In Cheol Bang (Ulsan Nat'l Institute of Science and Technology)
Two-Phase Flow Upscaling Method in a Macroporous Medium
Tanguy Herry (CEA), Emma Nguyen (CEA), Bruno Raverdy (CEA), Stéphane Mimouni (EDF)
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