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Kubota, Ryuzaburo; Koyama, Kazuya*; Moriwaki, Hiroyuki*; Yamada, Yumi*; Shimakawa, Yoshio*; Suzuki, Toru; Kawada, Kenichi; Kubo, Shigenobu; Yamano, Hidemasa
Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 10 Pages, 2017/04
This paper describes an analysis study on the initiating phase of the ATWS events with SAS4A in order to confirm the appropriateness of the core design for the medium-scale SFR (750MWe-1765MWt). Not using a conventional lumping method that multiple fuel sub-assemblies having a similar characteristic were assigned to one channel (representing fuel assembly in SAS4A), each channel represents only the sub-assemblies of identical operating condition. In addition, the detailed power and reactivity distribution were set reflecting the change of insertion position of control rods. Applying these detailed analysis conditions, the SAS4A analyses were performed for unprotected loss-of-flow (ULOF) and unprotected transient overpower (UTOP) during both of the nominal power and the partial power operation. As a result, more proper event progression including incoherency of events especially fuel dispersion after fuel failure was successfully evaluated and then this analysis study suggested that the power excursion with prompt criticality leading to large mechanical energy release can be prevented in the initiating phase of the current design.
Ikeda, Kazumi*; Homma, Yuto*; Moriwaki, Hiroyuki*; Oki, Shigeo
Proceedings of 2014 International Congress on the Advances in Nuclear Power Plants (ICAPP 2014) (CD-ROM), p.1175 - 1183, 2014/04
Moriwaki, Hiroyuki*; Kan, Taro*; Oki, Shigeo
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no abstracts in English
Oki, Shigeo; Sugino, Kazuteru; Moriwaki, Hiroyuki*; Tsuboi, Toru*
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no abstracts in English
Hasegawa, Takashi*; Kan, Taro*; Moriwaki, Hiroyuki*; Tokizaki, Minako*; Yamano, Hidemasa; Takano, Kazuya
no journal, ,
no abstracts in English
Sugino, Kazuteru; Nakazato, Wataru*; Moriwaki, Hiroyuki*
no journal, ,
JENDL-4.0 is planned to be applied to the core neutronics design for next generation FBRs. In order to improve the accuracy and reliability of the neutronics core design, reflection of the accumulated integral data is essential, which are obtained in critical facility experiments and power reactor tests. Additionally, the specific method of reflection should be prudently selected based on the comparison in advantages and disadvantages from the various points of view. The present study shows the general consistency between the calculation data of experiments/tests and the covariance data of cross-sections by comparing the prediction accuracies of neutronics core design using the combinations of several core design methods and uncertainty evaluation methods based on the constant set with JENDL-4.0.
Moriwaki, Hiroyuki*; Hibi, Koki*; Kan, Taro*; Oki, Shigeo; Kugo, Teruhiko; Okubo, Tsutomu
no journal, ,
no abstracts in English
Homma, Yuto*; Moriwaki, Hiroyuki*; Oki, Shigeo; Ikeda, Kazumi*
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no abstracts in English
Tsuboi, Toru*; Moriwaki, Hiroyuki*; Ogura, Masashi*; Hibi, Koki*; Maeda, Seiichiro; Ohgama, Kazuya; Chikazawa, Yoshitaka; Oki, Shigeo
no journal, ,
no abstracts in English
Moriwaki, Hiroyuki*; Ogura, Masashi*; Kan, Taro*; Oki, Shigeo
no journal, ,
no abstracts in English
Kubota, Ryuzaburo; Suzuki, Toru; Kawada, Kenichi; Kubo, Shigenobu; Yamano, Hidemasa; Koyama, Kazuya*; Moriwaki, Hiroyuki*; Yamada, Yumi*; Shimakawa, Yoshio*
no journal, ,
A new methodology to obtain SAS4A input data of power and reactivity profile more consistent with the core design for various core states was consolidated. Using this methodology, SAS4A analyses on the initiating phase during ULOF and UTOP transients from the full power state and the low power state were performed. This analysis study suggests that the power excursion with prompt criticality leading to large mechanical energy release can be prevented in the initiating phase of the current design for the medium-scale Gen-IV loop-type SFR.
Oki, Shigeo; Kugo, Teruhiko; Nakazato, Wataru*; Moriwaki, Hiroyuki*
no journal, ,
no abstracts in English
Ogura, Masashi*; Moriwaki, Hiroyuki*; Okubo, Yoshiyuki*; Oki, Shigeo; Okubo, Tsutomu
no journal, ,
no abstracts in English
Oki, Shigeo; Kugo, Teruhiko; Nakazato, Wataru*; Moriwaki, Hiroyuki*
no journal, ,
no abstracts in English
Sugino, Kazuteru; Ohgama, Kazuya; Nakazato, Wataru*; Moriwaki, Hiroyuki*
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Towards realizations of the demonstration reactor in around 2025 and the commercialized reactor in around 2050, a investigation on the conceptual core design of the sodium-cooled fast reactor (JSFR: Japan Sodium-cooled Fast Reactor) is under going. This paper presents the elavuation of the core design prediction accuracy based on the studies related to the latest nuclear data.