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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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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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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BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
S. J. Gage, G. D. Atkinson, Jr., G. D. Bouchey
Nuclear Technology | Volume 17 | Number 3 | March 1973 | Pages 247-260
Technical Paper | Radioisotope | doi.org/10.13182/NT73-A31268
Articles are hosted by Taylor and Francis Online.
A 1-mg 252 Cf neutron source is employed for neutron activation analysis studies on short half-life isotopes utilizing a cyclic irradiation-count sequence. A pneumatic, rapid-transfer system is used to transport samples from the irradiation position near a neutron source to the counting position adjacent to a gamma-ray spectrometer. Improved sensitivities are achieved for shortlived isotopes by selecting the optimal or near optimal cyclic policies. Interference-free sensitivities for several isotopes of possible interest are determined and compared to sensitivities achieved by conventional, noncyclic neutron activation analysis. The enhancement of the shortlived components is demonstrated for complex photospectra. Finally, the usefulness of a cyclic activation-counting procedure mth the 252Cf source is demonstrated for the assay of enriched uranium suggesting potential special nuclear materials safeguards applications.
