CBZ is a general-purpose reactor physics analysis code system, and FRBurner, which focuses on fast reactor burnup calculations, was developed recently with diverse combinations of available methodologies. Verification of this module is conducted with the OECD/NEA fast rector benchmark since this benchmark provides various types of fast reactors. Four key reactor physics parameters, effective neutron multiplication factor k eff , effective delayed neutron fraction β eff , sodium void reactivity ∆ρ void and Doppler reactivity ∆ρ Doppler are the focus and compared to two references provided by JAEA and CEA, respectively. The biases between the results from FRBurner and the JAEA and CEA references on each of the above key parameters are less than 0.5%, 1%, 3% and 7%, and less than 1.0%, 4%, 12%, and 12%, respectively. The comparison indicates that the FRBurner module would provide acceptable results for general-type fast reactor physics analysis in research. As one innovation, the detailed burnup chain model, which is significantly different from a generally-used pseudo fission product model in fast reactor neutronic analysis, is applied in FRBurner. The detailed burnup chain model helps FRBurner explicitly provide information about the inventory of fission products for nuclear waste management and spent fuel reprocessing.
Experimental analysis of the sample reactivity measured in the SEG experiment is carried out with the deterministic reactor physics code system CBZ with the recent evaluated nuclear data files, JENDL-4.0, ENDF/B-VIII.0 and JEFF-3.3.Since the systems to be analysed are fast-thermal coupled ones, 211-energy group neutron reaction cross section libraries applicable to both the fast and thermal neutron systems are generated and utilized. In the multi-group library generation, the recentlydeveloped FRENDY and FRENDY/MG codes are used. Forward and adjoint neutron fluxes at the sample position are calculated by solving the neutron transport equation, and the sample reactivity is obtained by the first-order perturbation calculations. In order to simplify the systems calculated, two-dimensional cylinder model is prepared based on the previous work.Whereas the simplified model is employed, generally the reactivity of many different samples is well predicted by the calculations in comparison with the experimental uncertainties. On some of the samples, large discrepancies of the C/E values from unity are observed, and also relatively large differences in the C/E values among different nuclear data files are observed. These information are still useful for future development of the 1
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