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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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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.
Darrell F. Newman
Nuclear Technology | Volume 19 | Number 2 | August 1973 | Pages 66-83
Technical Paper | Reactor | doi.org/10.13182/NT73-A31322
Articles are hosted by Taylor and Francis Online.
The temperature dependence of k∞ for a graphite-moderated ThO2-PuO2-fueled lattice has been measured in the high temperature lattice test reactor. Values of measured at equilibrium temperatures from 20 to 1000°C serve as a benchmark for evaluating computational methods and cross sections used in the design of a plutonium-fueled high temperature gas-cooled reactor (HTGR). The calculated and measured changes of k∞ with temperature are in agreement. However, the magnitudes of calculated values are ∼0.8% higher than the measured values for k∞. When plutonium is used as the initial fissile fuel, the temperature coefficient of reactivity is changed favorably from that of an HTGR lattice fueled initially with 235 U. The reactivity decrease associated with elevating this plutonium-thorium fuel to operating temperature is ∼30% less than that obtained with 235U-Th fuel, so the excess reactivity for which the control system must compensate is reduced with plutonium fueling. Above the operating temperature range, plutonium tends to make the temperature coefficient of the HTGR more negative due to increased neutron capture in the 1.06-eV resonance of 240Pu. This effect will improve the self-limiting characteristics of the reactor during a power excursion.