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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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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Latest News
NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
H. O. Menlove, R. A. Forster, D. L. Matthews
Nuclear Technology | Volume 19 | Number 3 | September 1973 | Pages 181-187
Technical Paper | Analysis | doi.org/10.13182/NT73-A15880
Articles are hosted by Taylor and Francis Online.
An 124Sb-Be(γ,n) assay system has been designed and fabricated for the measurement of fissile content in small samples, fuel rods, and solutions. The instrument uses multiple 4He gas tube detectors to count fast neutrons induced in the assay sample by the 124Sb-Be source neutrons. The 4He detectors are biased to count only neutrons with energies above the 26- and 360-keV source neutrons. Computer calculations were used to optimize the design of the irradiation unit, giving a factor of ∼3 improvement in the induced fission rate. The assay unit has been applied to the measurement of small UO2 samples, pressurized water and boiling water reactor fuel rods, and high temperature gas-cooled reactor fuel.
