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‎docs/2026_data_publication/bibliography.bib‎

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file = {Full Text PDF:/home/luke/snap/zotero-snap/common/Zotero/storage/Q8PQXJ6I/Leconte et al. - 2024 - Accurate measurements of delayed neutron data for reactor applications methodology and application.pdf:application/pdf},
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}
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@techreport{nobreENDFBVIII12024,
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title = {{ENDF}/{B}-{VIII}.1},
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url = {https://www.osti.gov/biblio/2571019},
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institution = {Brookhaven National Lab},
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author = {Nobre, G. and Capote, R. and Pigni, M. and Trkov, A. and Mattoon, C. and Neudecker, D. and Brown, D. and Chadwick, M. and Kahler, A. and Kleedtke, N. and Zerkle, M. and Hawari, A. and Chapman, C. and Fleming, N. and Wormald, J. and Ramić, K. and Danon, Y. and Gibson, N. and Brain, P. and Paris, M. and Hale, G. and Thompson, I. and Barry, D. and Stetcu, I. and Haeck, W. and Lovell, A. and Mumpower, M. and Potel, G. and Kravvaris, K. and Noguere, G. and McDonnell, J. and Carlson, A. and Dunn, M. and Kawano, T. and Wiarda, D. and Al-Qasir, I. and Arbanas, G. and Arcilla, R. and Beck, B. and Bernard, D. and Beyer, R. and Brown, J. and Cabellos, O. and Casperson, R. and Cheng, Y. and Chimanski, E. and Coles, R. and Cornock, M. and Cotchen, J. and Crozier, J. and Cullen, D. and Daskalakis, A. and Descalle, M.-A. and DiJulio, D. and Dimitriou, P. and Dreyfuss, A. and Durán, I. and Ferrer, R. and Gaines, T. and Gillette, V. and Gert, G. and Guber, K. and Haverkamp, J. and Herman, M. and Holmes, J. and Hursin, M. and Jisrawi, N. and Junghans, A. and Kelly, K. and Kim, H. and Kim, K. and Koning, A. and Koštál, M. and Laramee, B. and Lauer-Coles, A. and Leal, L. and Lee, H. and Lewis, A. and Malec, J. and Damián, J. and Marshall, W. and Mattera, A. and Muhrer, G. and Ney, A. and Ormand, W. and Parsons, D. and Percher, C. and Pritychenko, B. and Pronyaev, V. and Qteish, A. and Quaglioni, S. and Rapp, M. and Ressler, J. and Rising, M. and Rochman, D. and Romano, P. and Roubtsov, D. and Schnabel, G. and Schulc, M. and Siemers, G. and Sonzogni, A. and Talou, P. and Thompson, J. and Trumbull, T. and Marck, S. and Vorabbi, M. and Wemple, C. and Wendt, K. and White, M. and Wright, R.},
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month = aug,
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year = {2024}
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year = {2024},
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doi = {10.11578/endf/2571019},
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}
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@techreport{piksaikin_new_2019,
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title = {New {Aggregate} {Data} in the {IAEA} {Reference} {Database} for {Beta}-delayed {Neutron} {Emission}},
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url = {https://nds.iaea.org/records/y965e-r8511},
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doi = {10.61092/iaea.y3a1-394h},
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abstract = {No description available},
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language = {en},
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number = {INDC(NDS)-0784},
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urldate = {2026-04-07},
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institution = {IAEA},
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author = {Piksaikin, V. M. and Egorov, A. S. and Gremyachkin, D. E. and Mitrofanov, K. V.},
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year = {2019},
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file = {Full Text PDF:/home/luke/snap/zotero-snap/common/Zotero/storage/FJAS9PLV/Piksaikin et al. - New Aggregate Data in the IAEA Reference Database for Beta-delayed Neutron Emission.pdf:application/pdf},
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}

‎docs/2026_data_publication/images/b71/section.tex‎

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\begin{figure}
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\centering
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\includegraphics[width=0.5\linewidth]{images/b71/dnp_yield.png}
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\caption{The fraction of the delayed neutron yield from particular \glspl{DNP} from ENDF/B-VII.1 nuclear data. The six \glspl{DNP} with the largest delayed neutron yield contributions approximately 50\% of the total delayed neutrons per fission event. The remaining 212 \glspl{DNP} provide approximately 50\% of the total delayed neutron yield.}
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\caption{The fraction of the delayed neutron yield from particular \glspl{DNP} from ENDF/B-VII.1 nuclear data. The six \glspl{DNP} with the largest delayed neutron yield contribute approximately 50\% of the total delayed neutrons per fission event. The remaining 212 \glspl{DNP} provide approximately 50\% of the total delayed neutron yield.}
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\label{fig:b71-dnp-yield}
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\end{figure}
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\begin{table}[]
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\centering
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\caption{ENDF/B-VII.1 nuclear data delayed neutron yield and average half-life values.}
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\begin{tabular}{lrl}
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\begin{tabular}{lll}
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\hline
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Parameter & Value & Units\\
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\hline

‎docs/2026_data_publication/images/b80/section.tex‎

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\begin{table}[]
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\centering
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\caption{ENDF/B-VIII.0 nuclear data delayed neutron yield and average half-life values.}
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\begin{tabular}{lrl}
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\begin{tabular}{lll}
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\hline
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Parameter & Value & Units\\
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\hline
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Table \ref{tab:b80-PCCi} shows the ten largest $PCC_i$ terms, which reveals which \glspl{DNP} have the greatest impact on the \gls{DNP} group parameters $\nu_{d,k}$ and $\tau_k$.
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These results are similar to those presented in Section \ref{sec:b71} using ENDF/B-VII.1 data.
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The main changes are due to the presence of arsenic-86 and 87, which was not present in the ten largest \glspl{PCC} for ENDF/B-VII.1 data.
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The main changes are due to the presence of $^{86}$As and $^{87}$As, which were not present in the ten largest \glspl{PCC} for ENDF/B-VII.1 data.
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\begin{table}[]
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\centering

‎docs/2026_data_publication/images/hybrid/section.tex‎

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However, it is also possible to combine datasets, mixing the cumulative fission yields, emission probabilities, and half-lives.
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Figure \ref{fig:hybrid-nu-heatmap} shows heatmaps of the total delayed neutron yield $\nu_d (I)$ plotted against different cumulative fission yield and emission probability datasets.
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Although it is expected that the half-life dataset should not have an effect, only the nuclides present in all three datasets is included.
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This means that using the JEFF-3.1.1 half-lives results in a decrease to the total delayed neutron yield due to missing \gls{DNP} present in the ENDF datasets.
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This means that using the JEFF-3.1.1 half-lives results in a decrease to the total delayed neutron yield due to missing \glspl{DNP} present in the ENDF datasets.
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Interestingly, this has a larger effect on the ENDF cumulative fission yield calculated delayed neutron yields compared to those from JEFF-3.1.1 and JENDL-5.
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This is because the ENDF data has large \glspl{PCC} for certain \glspl{DNP}, such as $^{88}$As, that are not included in JEFF-3.1.1.
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This indicates the cumulative fission yields for these \glspl{DNP} may be over-reported in ENDF data compared to JENDL-5 and JEFF-3.1.1.
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\end{tabular}
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\begin{tablenotes}
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\small
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\item[*] ENDF/B-VIII.1 did not resolved the delayed neutron yield discrepancy present in the previous ENDF versions.
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\item[*] ENDF/B-VIII.1 did not resolve the delayed neutron yield discrepancy present in the previous ENDF versions.
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\end{tablenotes}
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\end{threeparttable}
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\label{tab:total-delnu-compare-net}
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\end{table}
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\subsubsection{Nuclear Data Comparisons}
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The results thus far have indicated potential discrepancies in the ENDF cumulative fission yields for \glspl{DNP}.
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The results thus far have indicated potential discrepancies in the ENDF cumulative fission yields for the \glspl{DNP}.
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To investigate this, cumulative fission yield differences between JENDL-5 and ENDF/B-VIII.0\footnote{Analysis with ENDF/B-VIII.1 gives the same results.} are compared for the \glspl{DNP} with the largest delayed neutron yield $\nu_d(I)$ contribution differences.
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This analysis showed there are two \glspl{DNP} alone that account for 67\% of the delayed neutron yield difference: $^{86}$As and $^{137}$Sb.
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The $^{86}$As yield difference primarily comes from the cumulative fission yield difference, which is $540 \pm 90$ $pcm$ larger in ENDF/B-VIII.0 than JENDL-5, and leads to a delayed neutron yield difference of $191 \pm 32$ $pcm$.
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The top four \glspl{DNP} with the largest yield differences are $^{94}$Rb, $^{98m}$Y, $^{85}$As, and $^{89}$Br which are all present in both datasets and have both negative and positive differences\footnote{$^{94}$Rb is larger in JENDL-5 by 54 $pcm$, $^{98m}$Y is larger in JEFF-3.1.1 by 52 $pcm$, $^{85}$As is larger in JENDL-5 by 39 $pcm$, and $^{89}$Br is larger in JEFF-3.1.1 by 21 $pcm$.}.
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Instead, the difference comes from many small $\nu_d$ contributions from JEFF-3.1.1 that are smaller than those in JENDL-5.
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This is shown in Figure \ref{fig:hybrid-hist-jeff-jendl}, which shows the JENDL-5 delayed neutron yields subtracted from the JEFF-3.1.1 delayed neutron yields using histograms with bin widths of 10 $pcm$.
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These small differences are displayed in Figure \ref{fig:hybrid-hist-jeff-jendl}, which shows the JENDL-5 delayed neutron yields subtracted from the JEFF-3.1.1 delayed neutron yields using histograms with bin widths of 10 $pcm$.
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Figure \ref{fig:hybrid-hist-jeff-jendl}(a) shows the histogram for the 123 \glspl{DNP} present in both datasets.
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This histogram shows in the two largest bins of 0 to 10 $pcm$ and -10 to 0 $pcm$ there are 62 \glspl{DNP} with an average $\Delta \nu_{d,i}$ of 0.90 $pcm$ contributing a total of 55.5 $pcm$, while there are 51 \glspl{DNP} with an average $\Delta \nu_{d,i}$ of -1.22 $pcm$ contributing a total of -62.2 $pcm$, respectively.
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The average $\Delta \nu_{d,i}$ when using the 123 \glspl{DNP} present in both datasets is -0.62 $pcm$, which comes from many small contributions as well as the seven \glspl{DNP} with a $\Delta \nu_{d,i}$ less than -10 $pcm$, though this is slightly offset by the three \glspl{DNP} with a $\Delta \nu_{d,i}$ greater than 10 $pcm$.
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This histogram shows in the two largest bins of 0 to 10 $pcm$ and $-10$ to 0 $pcm$ there are 62 \glspl{DNP} with an average $\Delta \nu_{d,i}$ of 0.90 $pcm$ contributing a total of 55.5 $pcm$, while there are 51 \glspl{DNP} with an average $\Delta \nu_{d,i}$ of $-1.22$ $pcm$ contributing a total of $-62.2$ $pcm$, respectively.
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The average $\Delta \nu_{d,i}$ when using the 123 \glspl{DNP} present in both datasets is $-0.62$ $pcm$, which comes from many small contributions as well as the seven \glspl{DNP} with a $\Delta \nu_{d,i}$ less than $-10$ $pcm$, though this is slightly offset by the three \glspl{DNP} with a $\Delta \nu_{d,i}$ greater than 10 $pcm$.
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Figure \ref{fig:hybrid-hist-jeff-jendl}(b) shows the histogram for the 280 unique nuclides between both datasets.
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This histogram shows in the two largest bins of 0 to 10 $pcm$ and -10 to 0 $pcm$ there are 85 \glspl{DNP} with an average $\Delta \nu_{d,i}$ of 0.66 $pcm$ contributing a total of 55.9 $pcm$, while there are 184 \glspl{DNP} with an average $\Delta \nu_{d,i}$ of -0.49 $pcm$ contributing a total of -90.7 $pcm$, respectively.
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The average $\Delta \nu_{d,i}$ when using the 280 \glspl{DNP} present in either dataset is -0.43 $pcm$, which comes from many small contributions as well as the seven \glspl{DNP} with a $\Delta \nu_{d,i}$ less than -10 $pcm$, though this is slightly offset by the three \glspl{DNP} with a $\Delta \nu_{d,i}$ greater than 10 $pcm$.
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This histogram shows in the two largest bins of 0 to 10 $pcm$ and $-10$ to 0 $pcm$ there are 85 \glspl{DNP} with an average $\Delta \nu_{d,i}$ of 0.66 $pcm$ contributing a total of 55.9 $pcm$, while there are 184 \glspl{DNP} with an average $\Delta \nu_{d,i}$ of $-0.49$ $pcm$ contributing a total of $-90.7$ $pcm$, respectively.
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The average $\Delta \nu_{d,i}$ when using the 280 \glspl{DNP} present in either dataset is $-0.43$ $pcm$, which comes from many small contributions as well as the seven \glspl{DNP} with a $\Delta \nu_{d,i}$ less than $-10$ $pcm$, though this is slightly offset by the three \glspl{DNP} with a $\Delta \nu_{d,i}$ greater than 10 $pcm$.
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The average is smaller in magnitude compared to using only the common \glspl{DNP} because there are many additional smaller contributions present when account for the many less impactful \glspl{DNP} present in JENDL-5 that are not present in JEFF-3.1.1.
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\includegraphics[width=0.45\linewidth]{images/hybrid/yield_diff_hist_present_both.png}
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}
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\hspace{0.05\linewidth}
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\subfloat[The JEFF-3.1.1 \gls{DNP} $\nu_{d_i}$ minus the JENDL-5 \gls{DNP} $\nu_{d,i}$ for all \glspl{DNP} present in either dataset.]{
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\subfloat[The JEFF-3.1.1 \gls{DNP} $\nu_{d_i}$ minus the JENDL-5 \gls{DNP} $\nu_{d,i}$ for every \gls{DNP} present in either dataset.]{
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\includegraphics[width=0.45\linewidth]{images/hybrid/yield_diff_hist_all.png}
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}
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\caption{These histograms show the difference in the individual \gls{DNP} yield contribution $\Delta \nu_{d,i}$ between the JEFF-3.1.1 dataset and the JENDL-5 dataset using bin widths of 10 $pcm$. Using all \gls{DNP} present in either dataset results in an average delayed neutron yield contribution difference $\Delta \nu_{d,i}$ of -0.43 $pcm$, while using only \gls{DNP} present in both datasets results in an average delayed neutron yield contribution difference $\Delta \nu_{d,i}$ of -0.62 $pcm$.}

‎docs/2026_data_publication/images/iaea/section.tex‎

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\begin{table}[]
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\centering
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\caption{IAEA beta-delayed neutron emission database and JENDL-5 nuclear data delayed neutron yield and average half-life values.}
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\begin{tabular}{lrl}
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\begin{tabular}{lll}
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\hline
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Parameter & Value & Units\\
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\hline
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Table \ref{tab:iaea-jendl5-Ui} shows the ten largest $U_i$ terms, which corresponds to which \glspl{DNP} have the largest uncertainties relative to their impact on the \gls{DNP} group parameters $\nu_{d,k}$ and $\tau_k$.
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These ten \glspl{DNP} do not overlap at all with Table \ref{tab:iaea-jendl5-PCCi}, indicating that the JENDL-5 cumulative fission yields and IAEA beta-delayed neutron emission database have small relative uncertainties for the \glspl{DNP} in Table \ref{tab:iaea-jendl5-PCCi} as otherwise those \glspl{DNP} would dominate Table \ref{tab:iaea-jendl5-Ui}.
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Interestingly, it appears that cobalt has several isotopes that have large $U_i$ values, indicating that element has large relative uncertainties in its nuclear data relative to its impact on the \gls{DNP} group parameters.
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Interestingly, it appears that cobalt has several isotopes that have large $U_i$ values, indicating that cobalt has large relative uncertainties in its nuclear data relative to its impact on the \gls{DNP} group parameters.
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\begin{table}[]
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\centering
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Figure \ref{fig:iaea-jendl-bar-uiv} gives a more detailed view on which \gls{DNP} values specifically lead to the large $U_i$ values.
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This offers slightly more insight than Table \ref{tab:iaea-jendl5-Ui}, which sums over the various \gls{DNP} values.
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This figure shows that the half-lives $\tau$ and emission probabilities $P_n$ are the primary drivers of $U_{i}$, at least for the ten most impactful \glspl{DNP}.
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This indicates that the JENDL-5 cumulative fission yields offer sufficiently relative uncertainties compared to the relative uncertainties from the IAEA beta-delayed neutron emission database.
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This indicates that the JENDL-5 cumulative fission yields offer small relative uncertainties compared to the relative uncertainties from the IAEA beta-delayed neutron emission database for \glspl{DNP} that have more significant effects on the \gls{DNP} group parameters.
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\begin{figure}

‎docs/2026_data_publication/images/jeff311/section.tex‎

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\begin{table}[]
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\centering
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\caption{JEFF-3.1.1 nuclear data delayed neutron yield and average half-life values.}
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\begin{tabular}{lrl}
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\begin{tabular}{lll}
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\hline
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Parameter & Value & Units\\
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This offers slightly more insight than Table \ref{tab:jeff311-Ui}, which sums over the various \gls{DNP} values.
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For instance, these results show that $^{98}$Y has a large contribution of its uncertainty-weighted sensitivity come from emission probability uncertainty, with a smaller contribution from its half-life uncertainty.
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It can also be seen that $^{137}$I is not in Figure \ref{fig:jeff311-bar-uiv} even though it is in Table \ref{tab:jeff311-Ui}, indicating that its uncertainty-weighted sensitivity comes from the sum of several smaller components rather than one large term.
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Specifically, 54.5\% comes from emission probability uncertainty, 42.8\% comes from concentration uncertainty, and the remainder comes from half-life uncertainty.
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Specifically, 54.5\% of its $U_i$ comes from emission probability uncertainty, 42.8\% comes from concentration uncertainty, and the remainder comes from half-life uncertainty.
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\begin{figure}

‎docs/2026_data_publication/images/jendl5/section.tex‎

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\begin{table}[]
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\centering
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\caption{JENDL-5 nuclear data delayed neutron yield and average half-life values.}
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\begin{tabular}{lrl}
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\begin{tabular}{lll}
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\hline
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Parameter & Value & Units\\
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Four out of ten of these \glspl{DNP} are also in Table \ref{tab:iaea-jendl5-Ui}, though there are differences due to the emission probability and half-life differences.
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One notable difference is $^{102}$Sr, which has a $U_i$ value of $3.63 \times 10^{13}$.
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This value is significantly larger than any other value from any other dataset because it has an emission probability of $(6.245 \times 10^{-17}) \pm 0.02$.
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This means that the relative uncertainty in Equation \eqref{eq:Uiv} works out to be $3.2 \times 10^{-14}$, which is exceedingly large.
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This means that the relative uncertainty in Equation \eqref{eq:Uiv} works out to be $3.2 \times 10^{14}$, which is exceedingly large.
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To continue conducting the analysis, the contribution of $^{102}$Sr is ignored, treating the emission probability as 0 for this analysis.
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\begin{table}[]

‎docs/2026_data_publication/main.pdf‎

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