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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.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
NRC okays construction permits for Hermes 2 test facility
The Nuclear Regulatory Commission announced yesterday that it has directed staff to issue construction permits to Kairos Power for the company's proposed Hermes 2 nonpower test reactor facility to be built at the Heritage Center Industrial Park in Oak Ridge, Tenn. The permits authorize Kairos to build a facility with two 35-MWt test reactors that would use molten salt to cool the reactor cores.
Ross Pivovar, Rebecca Owston
Nuclear Science and Engineering | Volume 197 | Number 4 | April 2023 | Pages 686-702
Computer Code Abstract | doi.org/10.1080/00295639.2022.2126718
Articles are hosted by Taylor and Francis Online.
The features and equations of MixcoatlTM are presented in Part 1 of this two-paper series with no discussion on physics verification. The verification of Mixcoatl specifically for prismatic fuel designs/shell-and-tube–like designs is presented here. Furthermore, conclusions are made on the uncertainties that are extendable to the results of other codes that utilize a one-dimensional (1D) flow assumption with Nusselt correlations. Demonstration of commonly used scenarios for reactor designs is explored, and applicable ranges/deviations from the 1D flow assumption are investigated.