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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
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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
Strontium: Supply-and-demand success for the DOE’s Isotope Program
The Department of Energy’s Isotope Program (DOE IP) announced last week that it would end its “active standby” capability for strontium-82 production about two decades after beginning production of the isotope for cardiac diagnostic imaging. The DOE IP is celebrating commercialization of the Sr-82 supply chain as “a success story for both industry and the DOE IP.” Now that the Sr-82 market is commercially viable, the DOE IP and its National Isotope Development Center can “reassign those dedicated radioisotope production capacities to other mission needs”—including Sr-89.
W. Primak, L. H. Fuchs
Nuclear Science and Engineering | Volume 2 | Number 1 | February 1957 | Pages 49-56
doi.org/10.13182/NSE57-A15572
Articles are hosted by Taylor and Francis Online.
A method for using a saturating property to formulate a linear dosage scale is developed. The method is applied to the determination of the radiation damage rate for graphite in a nuclear reactor using the per cent decrease in electrical conductivity as the property. The damage rates in a number of irradiation facilities of the CP-3, CP-3′, and X-10 reactors are given. It is conclusively shown that the thermal neutron flux cannot be used to indicate the damage rate, for the one can be varied by more than an order of magnitude with respect to the other.
