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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 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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Latest News
NWMO to select Canadian repository site this year
Canada’s Nuclear Waste Management Organization, a not-for-profit organization responsible for the long-term management of the country’s intermediate- and high-level radioactive waste, is set to select a site for a deep geologic repository by the end of the year.
Rodolfo M. Ferrer, Joshua M. Hykes
Nuclear Science and Engineering | Volume 197 | Number 2 | February 2023 | Pages 333-350
Technical Paper | doi.org/10.1080/00295639.2022.2053491
Articles are hosted by Taylor and Francis Online.
The Spatially Dependent Self-Shielding (SDSS) method has been implemented into CASMO5 within the framework of Equivalence Theory. The Optimal Two-Term Rational (OTTR) approximation is extended in the SDSS method to the Stoker-Weiss treatment of concentric annular fuel subdivisions. Reference fuel-to-fuel probabilities are required by the OTTR and obtained by performing a series of fixed-source, two-dimensional transport calculations for individual pin cell types using the method of characteristics. Several algorithms used in searching for the OTTR coefficients are evaluated with the goal of obtaining the best practical accuracy at minimal computational cost. Numerical results are presented that provide a comparison of various choices of search algorithms and show improved accuracy obtained by increasing the degrees of freedom in the rational approximation. Spatial profiles of the 238U microscopic absorption cross sections in the resonance range obtained using the Distributed Resonance Integral (DRI) and SDSS methods are compared to reference results from Monte Carlo calculations. The comparison highlights the inherent advantages of SDSS over the previous DRI method.