Uncertainty Quantification with Monte Carlo Hauser-Feshbach Calculations of Prompt Fission Neutrons and Gamma Rays PDF Download
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Languages : en
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Author: Theodore E. Fessler
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Category : Nuclear physics
Languages : en
Pages : 54
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Languages : en
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Monte Carlo simulations for particle and [gamma]-ray emissions from an excited nucleus based on the Hauser-Feshbach statistical theory are performed to obtain correlated information between emitted particles and [gamma]-rays. We calculate neutron induced reactions on 51V to demonstrate unique advantages of the Monte Carlo method. which are the correlated [gamma]-rays in the neutron radiative capture reaction, the neutron and [gamma]-ray correlation, and the particle-particle correlations at higher energies. It is shown that properties in nuclear reactions that are difficult to study with a deterministic method can be obtained with the Monte Carlo simulations.
Author: Jilang Miao
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Languages : en
Pages : 327
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Monte Carlo methods have mostly been used as a benchmark tool for other transport and diffusion methods in nuclear reactor analysis. One important feature of Monte Carlo calculations is the report of the variance of the estimators as a measure of uncertainty. In the current production codes, the assumption of independence of neutron generations in Monte Carlo eigenvalue simulations leads to the oversimplified estimate of the uncertainty of tallies. The correlation of tallies between neutron generations can make reported uncertainty underestimated by a factor of 8 in assembly size tallies in a typical LWR. This work analyzes the variance/uncertainty convergence rate in Monte Carlo eigenvalue simulations and develops different methods to properly report the variance. To correct the underestimated variance as a post-processing step, a simple correction factor can be calculated from the correlation coefficients estimated from a sufficient number of active generations and fitted to decreasing exponentials. If the variance convergence rate is needed before or during the simulation to optimize the run strategy (number of generations and neutrons per generation), a discrete model can be constructed from the inactive generations that can predict the correlation behavior of the original problem. Since it is not efficient to perform variance correction to all tallies on all problems, a simple correlation indicator is also developed to quickly determine the potential impact of correlations on a given tally in a given problem. This can help decide if more complicated correction analysis or the use of independent simulations should be used to calculate the true variance. Run strategy to reduce correlations is also investigated by introducing the notion of delayed neutrons. A predictive model for the new source update scheme was developed to help identify optimal delayed neutron parameters before implementing in OpenMC. Optimal run strategies in terms of delayed bank size, frequency of delayed bank sampling and true simulation costs are proposed.
Author: Henry C. Honeck
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Category : Fermi surfaces
Languages : en
Pages : 30
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A program was developed for the ORACLE which computes the second moment of the slowing down distribution of neutrons in a mixture of elements. The program allows mixtures of up to eight elements, four of which have scattering, absorption, and transport cross sections, and four which have only absorption cross sections. Provision is made to calculate other properties of the slowing down system, such as the average diffusion coefficient, the resonance escape probability, and the squared first and last flight mean free paths.
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Languages : en
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Author: Jiaxin Wang
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Category :
Languages : en
Pages : 176
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Author: Theodore E. Fessler
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Category :
Languages : en
Pages : 1
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Two point-source, infinite-medium Monte Carlo codes were written for the IBM 704 computer. The codes simulate respectively gamma-ray and neutron transport from a monoenergetic source. A detailed description, including importance sampling methods, is given. Results showed good agreement with moments-method calculations for the same geometry. Calculations for 6-Mev gamma rays in tin provide data on the contribution of annihilation radiation to both the buildup factors and energy spectra. Calculations for 1-Mev gamma rays in water are also presented. The results of calculations for 6-Mev source neutrons in water show a peak in the energy spectrum which is found to be due to single scattering of source particles from oxygen. (Author).
Author: Roy Yih-Liang Yuan
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Category :
Languages : en
Pages : 300
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