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ANS, UCOR sign MOU for workforce development program
The American Nuclear Society and United Cleanup Oak Ridge have signed a memorandum of understanding that establishes a framework for collaboration to advance ANS workforce training and certification programs serving the nuclear industry.
According to the document, UCOR will provide “operational insights and subject matter expertise to inform ANS’s professional development and credentialing offerings, including the Certified Nuclear Professional [CNP] program.” The collaboration will strengthen UCOR’s workforce development efforts while advancing ANS’s mission to sustain and expand the national nuclear workforce pipeline and capabilities.
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.