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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
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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Latest News
Sam Altman steps down as Oklo board chair
Advanced nuclear company Oklo Inc. has new leadership for its board of directors as billionaire Sam Altman is stepping down from the position he has held since 2015. The move is meant to open new partnership opportunities with OpenAI, where Altman is CEO, and other artificial intelligence companies.
Junfeng Zhao, Yuanjie Sun, Yue Zhang, Zhigang Li, Hongtao Zhao, Qingyu Wang
Nuclear Technology | Volume 211 | Number 2 | February 2025 | Pages 214-224
Research Article | doi.org/10.1080/00295450.2024.2323257
Articles are hosted by Taylor and Francis Online.
The impact of CsPbBr3, known for its high atomic number and cross section with neutrons, on the gamma-ray and neutron shielding properties of CsPbBr3-polypropylene (PP) composite material was investigated in this study. Critical shielding parameters, including linear attenuation coefficient μ, mass attenuation coefficient μm, half-value thickness, tenth-value layer, and mean free path (MFP), were calculated using Phy-X/PSD software. Additionally, two types of gamma-ray buildup factors, i.e., exposure buildup factor and energy absorption buildup factor, were computed within the range of 0.015 to 15 MeV for depths up to 40 MFP. Furthermore, the neutron shielding ability was evaluated by determining the neutron total effective removal cross section. The results demonstrate that the incorporation of CsPbBr3 enhances the gamma-ray and neutron shielding characteristics of the CsPbBr3-PP composite material.
