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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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New consortium to address industry need for nuclear heat and power
Hoping to tackle a growing global demand for energy, The Open Group, a vendor-neutral technology and standards membership organization, has announced the formation of the Industrial Advanced Nuclear Consortium (IANC) to collaborate on finding advanced nuclear energy solutions to serve industrial customers.
H. L. Dodds, Jr., H. C. Honeck, D. E. Hostetler
Nuclear Science and Engineering | Volume 62 | Number 4 | April 1977 | Pages 751-756
Technical Note | doi.org/10.13182/NSE77-A15218
Articles are hosted by Taylor and Francis Online.
A coarse-mesh finite difference method has been developed for multidimensional, mixed-lattice reactor diffusion calculations, both statics and kinetics, in hexagonal geometry. Results obtained with the coarse-mesh (CM) method have been compared with a conventional mesh-centered finite difference method and with experiment. The results of this comparison indicate that the accuracy of the CM method for highly heterogeneous (mixed) lattices using one point per hexagonal mesh element (“hex”) is about the same as the conventional method with six points per hex. Furthermore, the computing costs (i.e., central processor unit time and core storage requirements) of the CM method with one point per hex are about the same as the conventional method with one point per hex.