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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.
G. A. Krist, C. G. Poncelet
Nuclear Science and Engineering | Volume 51 | Number 4 | August 1973 | Pages 347-375
Technical Paper | doi.org/10.13182/NSE73-A23272
Articles are hosted by Taylor and Francis Online.
An investigation of the stability of a nuclear power reactor subject to random macroscopic parameter variations is performed. An analysis procedure for determining the effect of stochastic coefficients on the stability in the mean and mean square of linear systems is presented. The procedure is based on Gaussian white process variations which can be shown to be governed by the Fokker-Planck equation. Moment equations are extracted from the Fokker-Planck equation and serve as system equations used for the stability analysis. It is shown that for some simple space-independent reactor models it is possible for random macroscopic parameter variation to destabilize in the mean and mean square a deterministically stable system. Conversely, the study has shown that under certain conditions random macroscopic variation of system parameters can also stabilize in the mean and mean square, a system which is deterministically unstable. A coupled-core spatial reactor model is utilized for the investigation of xenon instability. The results of this analysis again indicate that random macroscopic parameter variation can be a stabilizing or destabilizing influence. Analog simulations of linear systems with stochastic coefficients and a simple reactor model are used to verify the analysis procedure developed in this research.