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Hamase, Erina; Ohgama, Kazuya; Kawamura, Takumi*; Doda, Norihiro; Tanaka, Masaaki; Yamano, Hidemasa
Annals of Nuclear Energy, 195, p.110157_1 - 110157_14, 2024/01
Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)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.
Hamase, Erina; Ohgama, Kazuya; Kawamura, Takumi*; Doda, Norihiro; Yamano, Hidemasa; Tanaka, Masaaki
Proceedings of 12th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS12) (Internet), 9 Pages, 2022/10
To improve the prediction accuracy of the plant dynamics analysis code named Super-COPD, JAEA has joined the IAEA benchmark for the FFTF Loss of Flow Without Scram Test No.13. In the first blind phase, there was the challenge to perform outlet temperatures of fuel assemblies more accurately. Hence, the renewed analysis was performed with the whole core multi-channel model in which each assembly was modelled to simulate the radial heat transfer among assemblies and the flow redistribution induced by the buoyancy in the NC conditions. Then, to validate the coupled transient analysis between the whole core multi-channel model and the one-point kinetics model, the analysis considering major reactivity feedbacks such as GEM, assembly bowing was performed. As a result, the second peak of outlet temperatures was reproduced successfully, and it was observed that the plant dynamics analysis could follow the measured data.
Kawamura, Hidemasa*; Tatei, Kazuaki*; Nonaka, Tetsuo*; Obinata, Hideru*; Hattori, Tomoyasu*; Ogawa, Ai*; Kazama, Hideko*; Hamada, Nobuyuki*; Funayama, Tomoo; Sakashita, Tetsuya; et al.
Journal of Radiation Research, 50(2), p.161 - 169, 2009/03
Times Cited Count:7 Percentile:26.99(Biology)Harada, Kosaku*; Nonaka, Tetsuo*; Hamada, Nobuyuki*; Funayama, Tomoo; Sakurai, Hideyuki*; Sakashita, Tetsuya; Wada, Seiichi*; Kawamura, Hidemasa*; Hasegawa, Masatoshi*; Kobayashi, Yasuhiko; et al.
JAEA-Review 2006-042, JAEA Takasaki Annual Report 2005, P. 102, 2007/02
Tatei, Kazuaki*; Tamaki, Tomoaki*; Kawamura, Hidemasa*; Hamada, Nobuyuki*; Sakashita, Tetsuya; Funayama, Tomoo; Wada, Seiichi*; Kakizaki, Takehiko; Nonaka, Tetsuo*; Obinata, Hideru*; et al.
JAEA-Review 2006-042, JAEA Takasaki Annual Report 2005, P. 103, 2007/02
no abstracts in English
Harada, Kosaku*; Nonaka, Tetsuo*; Sakurai, Hideyuki*; Kawamura, Hidemasa*; Hasegawa, Masatoshi*; Nakano, Takashi*; Hamada, Nobuyuki*; Wada, Seiichi*; Kobayashi, Yasuhiko; Funayama, Tomoo; et al.
no journal, ,
no abstracts in English
Tatei, Kazuaki*; Tamaki, Tomoaki*; Kawamura, Hidemasa*; Nonaka, Tetsuo*; Obinata, Hideru*; Hattori, Tomoyasu*; Ogawa, Ai*; Kazama, Hideko*; Nakano, Takashi*; Izumi, Takashi*; et al.
no journal, ,
no abstracts in English
Harada, Kosaku*; Nonaka, Tetsuo*; Hamada, Nobuyuki*; Sakurai, Hideyuki*; Kawamura, Hidemasa*; Hasegawa, Masatoshi*; Kobayashi, Yasuhiko; Nakano, Takashi*
no journal, ,
no abstracts in English
Kawamura, Hidemasa*; Tatei, Kazuaki*; Nonaka, Tetsuo*; Obinata, Hideru*; Hattori, Tomoyasu*; Ogawa, Ai*; Kazama, Hideko*; Hamada, Nobuyuki*; Funayama, Tomoo; Sakashita, Tetsuya; et al.
no journal, ,
no abstracts in English
Hamase, Erina; Ohgama, Kazuya; Kawamura, Takumi*; Doda, Norihiro; Yamano, Hidemasa; Tanaka, Masaaki
no journal, ,
Validation of an analysis model for a plant dynamic analysis code named Super-COPD including neutronics calculation of a one-point reactor kinetics model necessitates the further work on the beyond design basis accident. Therefore, JAEA participated in IAEA benchmark for Loss of Flow without Scram (LOFWOS) test No.13 performed at the Fast Flux Test Facility (FFTF), and the transient analysis at the first blind phase considering with major reactivity feedback mechanisms was carried out. It was observed that the whole plant dynamics analysis could follow the measured data. As a future work, the gap conductance model for transient, the upper plenum of reactor vessel with dividing several regions or multi-dimensional modeling, and the core model that can evaluate the radial heat transfer rate more accurately will be refined.