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Report No.
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Analysis of Post-Irradiation Experiments on the Core Fuel composition of the Fast Experimental Reactor "JOYO" MK-I

Yokoyama, Kenji; Jin, Tomoyuki*

In the development of fast reactors, it is important to verify and improve the prediction accuracy of isotopic composition change by burnup. In this study, post irradiation experiment (PIE) data of fuel assemblies irradiated in the experimental fast reactor "JOYO" MK-I core was analyzed. As the isotopic composition after irradiation had been measured in the PIE, the authors selected to evaluate the rate of change of atomic number density (RC) by burnup. The RCs strongly depend on the error of the initial atomic number density. Therefore, the authors evaluated RCs based on the sample regression constants with the linear-square method in order to remove the dependency on the error of the initial atomic number density. The analysis was carried out for all the avajlable - 80 point PIE data on core fuel$$_{assemblies.}$$ In the analysis, the 70 group diffusion calculation with 3-dimensional Tri-Z geometry model was performed by using the nuclear data library JENDL-3.2, and the burn up calculation considering neutron spectrum in the irradiation position was carried out. As a result of the analysis, calculated value agreed with experimental values within 2--10 % on the main nuclides, such as U-235, U-236, U-238, Pu-239 and Pu-241. However, it is necessary to upgrade and verify the analysis method by using these PIE data since there is a room for improvement of the analysis models. 0n the other hand, the nuclear data library effect was also evaluated by using JENDL-3.3. It was found that JENDL-3.3 increased both RCs of U-236 and Pu-241 by -5% due to the revisions of U-235 and Pu-240 capture cross-sections. In the future, improvement of the analysis model and quantification of the error will make it possible to apply the PIE data of "JOYO" for the verification of these nuclear data.

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