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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.
L. H. Rovner, G. R. Hopkins
Nuclear Technology | Volume 29 | Number 3 | June 1976 | Pages 274-302
Technical Paper | Fusion Reactor Material / Material | doi.org/10.13182/NT76-A31593
Articles are hosted by Taylor and Francis Online.
The (low-atomic-number ceramic) materials carbon, SiC, Be2C, B4C, TiC, BN, Si3N4, Al2O3, and BeO provide a range of property values that are useful for evaluating range of applicability of low-atomic-number ceramic materials in fusion reactors. A survey of recent literature provides a base for conceptual design analyses of two first wall concepts: (a) a radiation-cooled simple plate liner and (b) a pressurized helium, forced convection-cooled tubular assembly. The first case is limited in heat load by maximum material temperature, and the second by either temperature or stress. Maximum temperatures are limited by vapor pressure or chemical reaction rates with plasma hydrogen, both resulting in release of impurities to the plasma. Silicon carbide and carbon appear most suitable for first wall materials, with estimated wall loading limits in the range from 1 to >5 MW/m2 of incident 14-MeV neutrons.