nureg/cr-6700 - Oak Ridge National Laboratory
nureg/cr-6700 - Oak Ridge National Laboratory
nureg/cr-6700 - Oak Ridge National Laboratory
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Section 7<br />
Recommendations<br />
Conclusions and<br />
7 CONCLUSIONS AND RECOMMENDATIONS<br />
The importance rankings in this report are designed to facilitate validation efforts related to the prediction of<br />
spent fuel isotopics and radiological decay properties of high-burnup spent fuel by identifying the nuclides<br />
that have the greatest impact in the application areas of interest and illustrate the variation in nuclide<br />
importance with burnup. These results also have potential application to establishing the degree of<br />
applicability of existing validation data to the high-burnup regime and may be useful to help identify the<br />
challenges that high-burnup fuel presents to existing computational methods and nuclear data.<br />
The availability of experimental data for code validation in the high-enrichment and high-burnup regimes is<br />
likely to be limited in the near term to isotopic assay measurements that are either underway or are being<br />
planned in support of <strong>cr</strong>iticality burnup <strong>cr</strong>edit activities in the United States and in other countries. Through<br />
these activities the experimental assay programs are seeking to compile a comprehensive database of spent<br />
fuel isotopics that is representative of the fuel types and assembly designs from operating LWRs.<br />
Because the experimental database for decay heat and radiation source-term validation data is likely to<br />
remain limited to low- and moderate-enrichment and burnup fuels in the near term, a separate-effects<br />
approach to code validation currently used in burnup <strong>cr</strong>edit may be a valuable, if not necessary, option for<br />
validating code predictions of spent fuel radiological decay properties in the high burnup regime. This<br />
approach relies on independently validating the depletion analysis methods used to predict the spent fuel<br />
compositions using isotopic assay data, and validating the isotopic response (e.g., isotopic reactivity worth in<br />
burnup <strong>cr</strong>edit applications, or energy release rate per decay for decay heat applications). Such a strategy for<br />
validating decay heat generation and radiation source-term predictions would be simplified by the fact that<br />
relatively few radioisotopes are responsible for the responses at high burnup. For example, the decay-heat<br />
generation rate for high-burnup fuel is dominated by fewer than 10 radionuclides that are responsible for<br />
about 95% of the total decay heat at 5-years cooling. After 100 years just four radionuclides account for<br />
about 85% of the decay heating. A similar trend is observed for the radionuclides important to radiation<br />
shielding.<br />
A separate-effects approach would also be simplified by the fact that the nuclide decay data parameters<br />
important in these application areas (recoverable energy per decay for decay heating and radiation emission<br />
spectra for source terms) are already relatively well established by measurements. Consequently, the<br />
accuracy of computer code predictions could be established to a high degree of confidence using measured<br />
isotopic inventory data alone. Unfortunately, many of the nuclides important to the burnup <strong>cr</strong>edit are for the<br />
most part different than those important to decay-heat and radiation-source-term analysis. However, some<br />
overlap does exist.<br />
It is recommended that consideration be given to expanding the isotopic assay measurements currently being<br />
planned within the United States in support of the burnup <strong>cr</strong>edit activities to include additional radionuclides<br />
important to decay heating and radiation-source-term applications. A review of the findings from this study<br />
suggests that relatively few new radionuclides are needed to provide a relatively comprehensive<br />
characterization of high-burnup spent fuel in the respective application areas. Also, several key<br />
radionuclides exist as parent-daughter pairs (e.g., 137 Cs− 137m Ba, 90 Sr− 90 Y, 144 Ce− 144 Pr) and therefore only one<br />
radionuclide in these pairs would require measurement since they exist in secular equilibrium (i.e., the<br />
activities of the parent and daughter product are equal). The selected parent or daughter could be chosen to<br />
optimize the coverage of different application areas.<br />
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