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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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June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
G. Ferran, W. Haeck, M. Gonin
Nuclear Science and Engineering | Volume 179 | Number 3 | March 2015 | Pages 285-301
Technical Paper | doi.org/10.13182/NSE14-64
Articles are hosted by Taylor and Francis Online.
This paper describes in detail a new method to calculate the integral that appears in the expression of cross-section Doppler broadening. This method is based on a Fourier transform and seems quite promising as our tests suggest it is able to reach any required precision within a reasonable amount of calculation time. Another method to calculate Doppler-broadened cross sections based on Gauss quadrature will be presented, even if it requires too much computation time to be of practical use. Both methods have been implemented in a new nuclear data-processing software called GAIA, which is currently under development at the French Institut de Radioprotection et de Sûreté Nucléaire. Results of the comparison of the broadened cross sections obtained with the GAIA methods and with the NJOY processing system are discussed in the paper.