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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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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.
R. C. Greenwood, R. G. Helmer, J W Rogers, N. D. Dudey, R. J. Popek, L. S. Kellogg, W. H. Zimmer
Nuclear Technology | Volume 25 | Number 2 | February 1975 | Pages 274-288
Technical Paper | Material Dosimetry | doi.org/10.13182/NT75-A24368
Articles are hosted by Taylor and Francis Online.
Foils of various nonfissile materials commonly utilized in neutron dosimetry were irradiated in the Coupled Fast Reactivity Measurement Facility and quantitatively gamma counted by five groups at four laboratories. Each laboratory used an independently calibrated Ge(Li) detector, and in some cases an NaI(Tl) detector also. These measurements were undertaken as a part of the Interlaboratory LMFBR Reaction Rate (ILRR) program. A primary goal of this initial set of measurements made under the ILRR program was to intercompare the reaction rates determined by the participating groups. The reaction rate values determined by the five groups were all in excellent agreement, generally consistent to within ±2% with respect to each other. Based upon this consistency and the quoted measurement errors, we would estimate that for most nonfissile dosimetry foils, where the nuclear data are adequate, reaction rates can be determined with an accuracy of ∼±2% (standard deviation uncertainty) using these techniques. This accuracy then easily surpasses the accuracy goal of ±5% (1σ uncertainty) of the ILRR program for nonfissile dosimetry foils. These reaction rates are of sufficient accuracy to be used to test and evaluate energy-dependent cross-section sets currently being evaluated in ENDF/B.