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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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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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Discovering, Making, and Testing New Materials: SRNL’s Center For Hierarchical Waste Form Materials
Savannah River National Laboratory researchers are building on the laboratory’s legacy of using cutting-edge science to effectively immobilize nuclear waste in innovative ways. As part of the Center for Hierarchical Waste Form Materials, SRNL is leveraging its depth of experience in radiological waste management to explore new frontiers in the industry.
L. Green, J. J. Ullo
Nuclear Science and Engineering | Volume 67 | Number 2 | August 1978 | Pages 172-183
Technical Paper | doi.org/10.13182/NSE78-A15434
Articles are hosted by Taylor and Francis Online.
The spatial distribution of the total neutron density from a 252Cf source in pure water was measured to high statistical precision at distances ranging from 11 to 80 cm from the source. Assuming the adequacy of the ENDF/B-IV hydrogen cross sections and reasonable constraints on the fission spectrum mean energy, good agreement between experiment and a one-dimensional transport calculation was obtained for both ENDF/B-III and -IV oxygen cross sections, with Version III being slightly better. However, small residual differences remained that could not be removed by adjustment of the spectrum mean energy alone.