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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.
2020 ANS Virtual Winter Meeting
November 16–19, 2020
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
Fusion Science and Technology
HALEU investment is key part of TerraPower’s demo proposal
TerraPower announced on September 15 that it plans to work with Centrus Energy to establish commercial-scale production facilities for the high-assay, low-enriched uranium (HALEU) needed to fuel many advanced reactor designs.
The proposed investment in HALEU fuel fabrication is tied to a TerraPower-led submittal to the Department of Energy’s Advanced Reactor Demonstration Program (ARDP), which was created to support the deployment of two first-of-a-kind advanced reactor designs within five to seven years. TerraPower would like one of those designs to be Natrium, the 345-MWe sodium fast reactor that it has developed with GE Hitachi Nuclear Energy.
Item ID: 700432|ISBN: 978-0-89448-769-9
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The 2019 M&C Conference attracted top theoreticians and practitioners from North America, South America, Europe, and Asia, continuing the tradition of being the premier gathering of mathematicians, computer scientists, physicists, and engineers devoted to solving computational challenges in nuclear science and technology. These proceedings include archival versions of the M&C presentations that took place over four days in more than 35 sessions. Some of the topics the papers in this proceedings cover are, deterministic transport methods, Monte Carlo methods and applications, general radiation transport, computational fluid dynamics and applications to nuclear thermal hydraulics, multiphysics simulations in nuclear science and engineering, nuclear data evaluations and assimilation of integral experiments, uncertainty qualification and security analysis.