Validation of the fast reactor plant dynamics analysis code Super-COPD using FFTF loss of flow without scram test #13

Hamase, Erina ; Ohgama, Kazuya   ; Kawamura, Takumi*; Doda, Norihiro  ; Tanaka, Masaaki  ; Yamano, Hidemasa   

To validate the fast reactor plant dynamics analysis code Super-COPD for the loss of flow without scram (LOFWOS) event, we participated in the IAEA benchmark for the LOFWOS test No.13 performed at the FFTF as one of the passive safety demonstration test. In the blind phase, there were challenges to reproduce outlet temperatures of fuel assemblies and the total reactivity. To improve the evaluation accuracy of them, the whole core model considering the radial heat transfer and interwrapper flow and the simplified assembly bowing reactivity model were introduced. As a result of the final phase, the second peak of outlet temperatures was reproduced successfully, and the total reactivity could generally follow the measured data. Super-COPD was validated for the LOFWOS event.