Predicting Correlation Coefficients for Monte Carlo Eigenvalue Simulations

Monte Carlo methods are most often considered as a reference for neutron transport simulations since very limited approximations are made abount nuclear data and system geometry. To report uncertainty of any tally evaluated as generation averages, the sample variance is divided by the number of acti...

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Bibliographic Details
Main Authors: Miao, Jilang (Contributor), Forget, Benoit Robert Yves (Contributor), Smith, Kord S. (Contributor)
Other Authors: Massachusetts Institute of Technology. Department of Nuclear Science and Engineering (Contributor)
Format: Article
Language:English
Published: American Nuclear Society, 2017-04-10T18:08:46Z.
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