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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.
James R. Deen, E. Linn Draper, Jr.
Nuclear Technology | Volume 25 | Number 2 | February 1975 | Pages 416-422
Technical Paper | Material Dosimetry | doi.org/10.13182/NT75-A24378
Articles are hosted by Taylor and Francis Online.
The absolute cumulative fission yield of 140Ba and the relative yields of 131I, 132Te, and 141Ce were measured for 232Th irradiated in a 252Cf fission spectrum of neutrons. The irradiation was performed using two 232Th foils in contact with a nominal 1-mg 252Cf source in a large evacuated area for 41 days. The absolute yield of 140Ba was deduced from an absolute measurement of its daughter product 140La using a calibrated NaI(Tl) detector. The activities of 131I, 132Te, and 141 Ce were measured relative to the 1596-ke V gamma ray of 140La using a 43-cm3 Ge(Li) detector. The fission rate for the yield measurement and the integral fission cross section were measured using mica solid-state track recorders.