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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!
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Nuclear Science and Engineering
June 2024
Nuclear Technology
Fusion Science and Technology
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Join ANS for a webinar on exploring background radiation
The American Nuclear Society, in partnership with the Department of Energy’s Office of Nuclear Energy, is hosting its next Educator Training event, “K-12 Classroom Investigations: Exploring Background Radiation,” this Thursday, May 16, from 6:00 to 7:00 p.m. (EDT).
Register now. The event is complimentary and open to all.
Technical Session|Experimental Thermal Hydraulics
Wednesday, August 23, 2023|10:45AM–12:25PM EDT|Cardozo
Session Chair:
Guanyu Su (UCB)
Session Organizer:
Bao-Wen Yang (DEDQ)
To access paper attachments, you must be logged in and registered for the meeting.
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Experimental Investigations of Material-Conjugated Subcooled Flow Boiling
10:45–11:05AM EDT
Mingfu He (Univ. New Mexico), Minghui Chen (Univ. New Mexico)
Paper
The Effect of Time Varying Axial Power Shape on Transient Critical Power Performance of BWR Fuel
11:05–11:25AM EDT
B. Ward (Global Nuclear Fuel Americas), S. Oh (Global Nuclear Fuel Americas), J. Andersen (Global Nuclear Fuel Americas), C. Heck (Global Nuclear Fuel Americas), D. Rock (Global Nuclear Fuel Americas), M. Sugawara (Global Nuclear Fuel Americas), J. Lamy (Global Nuclear Fuel Americas)
Presentation Slides (Visible to Attendees)
Steady-State and Power Transient Critical Heat Flux Experiments of FeCrAl and Zircaloy Claddings Under Saturated Pool Boiling
11:25–11:45AM EDT
Experimental Research About Corrosion Effect on Boiling Heat Transfer Performance of Plate-Type Samples with Micro-Structures
11:45AM–12:05PM EDT
Wei Xu (Shanghai Jiao Tong Univ.), Xiaojing Liu (Shanghai Jiao Tong Univ.), Kun Ouyang (Shanghai Jiao Tong Univ.), Xiaoqiang He (Nuclear Power Institute of China)
Presentation Video (Visible to Attendees) — Wei Xu
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