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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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Nuclear Science and Engineering
June 2025
Nuclear Technology
May 2025
Fusion Science and Technology
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.
Catherine Romano, Ram Venkataraman, David Glasgow, Ben Roach
Nuclear Technology | Volume 208 | Number 11 | November 2022 | Pages 1696-1703
Technical Paper | doi.org/10.1080/00295450.2022.2070353
Articles are hosted by Taylor and Francis Online.
The cross sections of 237Np and 238Np are important for accurate modeling and simulation of 238Pu in the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL). Uncertainties in these cross sections can impact the ability to predict and optimize the target design and loading for 238Pu production targets. The effective capture cross section of 237Np in the location of pneumatic tube 1 in HFIR was measured as a first step in the measurement of the 238Np capture and fission cross sections. This paper describes the flux measurements, 237Np experiments, and data analysis of the 237Np capture cross section in HFIR.
