Abstract
ABSTRACT An analysis of the Special Power Excursion Test III E-Core experiment was performed in order to confirm the calculation accuracy of the light-water-reactor core analysis code system, constructed by the authors, of the CASMO5 and the TRACE/PARCS for the reactivity-initiated accident (RIA) analysis. The influence of the resonance up-scatter model (RUM) and the effective Doppler temperature model (EDTM) in the CASMO5 on the Doppler reactivity feedback effect was also discussed through the comparison with the conventional calculation without those models and the perturbation calculation of the Doppler reactivity coefficient. The calculation results by the CASMO5/TRACE/PARCS mostly showed good agreement with the experimental data within the range of experimental uncertainty, which confirmed the calculation accuracy of the analysis code system for the RIA analysis. In the calculation, the JENDL-4.0 and the ENDF/B-VII.1 were used, however, obvious difference was not seen in the calculation results between the two nuclear data libraries. The influence of the RUM on the core parameters was less than that of the 10% increment of Doppler reactivity coefficient on the conventional calculation. The influence of the EDTM became large on the cold condition, which was the same tendency on the Doppler reactivity coefficient discussed in the previous studies.
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