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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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2021 Student Conference
April 8–10, 2021
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
Climate change needs an Operation Warp Speed
The government of the United States should throw its muscle behind ramping up a mammoth, rapid rollout of all forms of renewable energy through Operation Warp Speed, similar to what is being done with COVID-19, Clive Thompson writes in an Ideas column for Wired.
The rollout should include energy sources that we already know how to build—like solar and wind — but also experimental emerging sources such as geothermal and small nuclear, and cutting-edge forms of energy storage or transmission.
Christopher M. Perfetti, Bradley T. Rearden, William J. Marshall
Nuclear Science and Engineering | Volume 185 | Number 1 | January 2017 | Pages 139-158
Technical Paper | dx.doi.org/10.13182/NSE16-54
Articles are hosted by Taylor and Francis Online.
This study focuses on understanding the phenomena in Monte Carlo simulations known as undersampling, in which Monte Carlo tally estimates may not encounter a sufficient number of particles during each generation to obtain unbiased tally estimates. Steady-state Monte Carlo simulations were performed using the KENO Monte Carlo tools within the SCALE code system for models of several burnup credit applications with varying degrees of spatial and isotopic complexities, and the incidence and impact of undersampling on eigenvalue and flux estimates were examined. Using an inadequate number of particle histories in each generation was found to produce a maximum bias of ~100 pcm in eigenvalue estimates and biases that exceeded 10% in fuel pin flux tally estimates. Having quantified the potential magnitude of undersampling biases in eigenvalue and flux tally estimates in these systems, this study then investigated whether Markov Chain Monte Carlo convergence metrics could be integrated into Monte Carlo simulations to predict the onset and magnitude of undersampling biases. Five potential metrics for identifying undersampling biases were implemented in the SCALE code system and evaluated for their ability to predict undersampling biases by comparing the test metric scores with the observed undersampling biases. Of the five convergence metrics that were investigated, three (the Heidelberger-Welch relative half-width, the Gelman-Rubin Řc diagnostic, and tally entropy) showed the potential to accurately predict the behavior of undersampling biases in the responses examined.