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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 Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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 2024
Jan 2024
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Nuclear Science and Engineering
May 2024
Nuclear Technology
Fusion Science and Technology
Latest News
NRC updating GEIS rule for new nuclear technology
The Nuclear Regulatory Agency is issuing a proposed generic environmental impact statement (GEIS) for use in reviewing applications for new nuclear reactors.
In an April 17 memo, NRC secretary Carrie Safford wrote that the commission approved NRC staff’s recommendation to publish in the Federal Register a proposed rule amending 10 CFR Part 51, “Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions.”
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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