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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.
A. Calza-Bini, G. Cosoli, G. Filacchioni, M. Lanchi, A. Nobili, E. Pesce, U. Rocca, P. L. Rotoloni
Nuclear Technology | Volume 25 | Number 1 | January 1975 | Pages 103-112
Technical Paper | Fuel | doi.org/10.13182/NT75-A24353
Articles are hosted by Taylor and Francis Online.
The heat transfer coefficient between fuel and cladding has been measured in-pile for different types of Zircaloy-2 sheathed fuels: UO2 and UO2-PuO2 pellets, UO2 Vipac, and UO2-PuO2 Sphere-Pac sol-gel. The samples were tested in (a) instrumented rigs, in which fuel and cladding temperatures and nuclear and gamma-ray generated power were directly and continuously measured up to a heat rating of 500 W/cm, and in (b) a hydraulic rabbit at very high rating (over 1000 W/cm). Semiempirical correlations starting from known models of fuel/clad heat transfer, based on strong or weak fuel/clad interaction, fuel cracking, and decrease in gap conductance due to oxide micro layer formation on the cladding internal surface, have been set up to fit the experimental data.
