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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Hash Hashemian: Visionary leadership
As Dr. Hashem M. “Hash” Hashemian prepares to step into his term as President of the American Nuclear Society, he is clear that he wants to make the most of this unique moment.
A groundswell in public approval of nuclear is finding a home in growing governmental support that is backed by a tailwind of technological innovation. “Now is a good time to be in nuclear,” Hashemian said, as he explained the criticality of this moment and what he hoped to accomplish as president.
Nam Zin Cho, Seungsu Yuk, Han Jong Yoo, Sunghwan Yun
Nuclear Science and Engineering | Volume 175 | Number 3 | November 2013 | Pages 227-238
Technical Paper | doi.org/10.13182/NSE12-68
Articles are hosted by Taylor and Francis Online.
In current practice of nuclear reactor design analysis, the whole-core diffusion nodal method is used in which nodal parameters are provided by a single-assembly lattice physics calculation with the zero net current boundary condition. Thus, the whole-core solution is not transport, because the interassembly transport effect is not incorporated. In this paper, the overlapping local/global iteration framework that removes the limitation of the current method is described. It consists of two-level iterative computations: half-assembly overlapping local problems embedded in a global problem. The local problem can employ heterogeneous fine-group deterministic or continuous-energy stochastic (Monte Carlo) transport methods, while the global problem is a homogenized coarse-group transport-equivalent model based on partial current-based coarse-mesh finite difference methodology. The method is tested on several highly heterogeneous multislab problems and a two-dimensional small core problem, with encouraging results.