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Copy file name to clipboardExpand all lines: docs/2026_data_publication/main.tex
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This agrees with the same result calculated in this work of $0.01609\pm0.0008$.
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This work is also verified with the total delayed neutron yield $\nu_d$ from Leconte et al. from JEFF-3.1.1 cumulative fission yields combined with ENDF/B-VII.1 emission probabilities and half-lives.
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Specifically, this work calculates a value of $0.0157\pm0.0008$, which exactly agrees with the results from Leconte et al. \cite{leconte2020new}.
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Finally, there is also agreement with Huynh et al. using the JEFF-3.1.1 data to calculate the total delayed neutron yield of $0.0148\pm0.0008$\cite{huynh2014calculation}.
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For the first set of results, additional information will be included that is not included in the other sections.
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Specifically, the delayed neutron count rate will be provided as well as a comparison to the count rate from calculated from other \gls{DNP} group parameters in the literature.
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