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The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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Destruction of Ukrainian dam threatens Zaporizhzhia
A Soviet-era dam downstream from the Zaporizhzhia nuclear power plant in southeastern Ukraine collapsed last evening, causing the water level of the Kakhovka Reservoir north of the dam to drop and raising new concerns over the already jeopardized safety of the Russian-occupied nuclear facility, Europe’s largest. The reservoir supplies water for, among other things, Zaporizhzhia’s cooling systems.
Dan G. Cacuci, Mihaela Ionescu-Bujor
Nuclear Science and Engineering | Volume 165 | Number 1 | May 2010 | Pages 18-44
Technical Paper | doi.org/10.13182/NSE09-37B
Articles are hosted by Taylor and Francis Online.
This work presents a rigorous methodology for computing best-estimate predictive results using experimental information in conjunction with models of time-dependent and/or stationary systems. This methodology uses Bayes' theorem in conjunction with information theory to assimilate consistently all available experimental and computational uncertainty-afflicted information (including discretization-modeling errors) for obtaining best-estimate calibrated model parameters and responses, together with correspondingly reduced uncertainties. This new methodology also provides quantitative indicators for assessing the consistency among parameters and responses, for consequent acceptance or rejection of information within the overall assimilation procedure. The companion paper presents a paradigm application of this methodology for obtaining best-estimate parameters for a transient thermal-hydraulic benchmark system pertinent to reactor safety.