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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.
W. H. McCarthy, K. J. Perry, G. R. Hull, J. W. Bennett
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 171-186
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31184
Articles are hosted by Taylor and Francis Online.
Sixteen unencapsulated mixed-oxide fuel pins were irradiated in EBR-II to ∼5 at.% burnup at 16 kW/ft nominal peak linear power. The fuel fabrication parameters were varied within the ranges proposed for commercial liquid-metal fast breeder reactors (LMFBR) except that pin diameter was ∼15% larger than usually specified. No cladding failures occurred. Pin growth was substantially greater in Type 304L stainless-steel-clad fuel pins than in Type 316 clad elements. Fission gas release to the internal void volume ranged from 73 to 97%. Experimental burnup values were 10 to 12% less than calculated values and varied across the subassembly in a manner that indicated a significant fission rate elevation from an adjacent extra-worth driver subassembly. Substantial attack was found in the cladding at its inside surface and the extent of this attack (up to 0.009-in. intergranular penetration at about 1150°F) correlated with temperature but not with any fuel fabrication parameter. The penetrating fission product material contained Cs, Mo, and Te. The unusually large amount of fuel/fission product/cladding reaction may be related to the high carbon content in the mixed oxides and/or to a short high-temperature operating period.