Transient response of BWR core flow during simulated generator load rejection event

Masahiro Furuya, Takashi Hara, Shinya Mizokami

研究成果: Conference contribution

抄録

Integral Effects Test (IET) was conducted to investigate the effects of flow redistribution during the generator load rejection event by using the SIRIUS-F facility, which simulates boiling two-phase flow in a BWR core. Owing to the automatic controllers of a recirculation pump inverter and fine-control valves in the facility, the time series of signals of heat flux and mass flux were observed to agree well with those of target rapid flow-decrease events in the previous experimental series. This paper addresses the simulated generator load rejection event, during which the flow and power gradually decrease and the flow takes a turn toward recovery. As a result of the two-parallel channel experiment, mass flux of a hot channel is lower than that of the other during the initial stage. When the void fraction becomes smaller, mass flux of the hot channel is observed to become higher. This phenomenon can be accurately demonstrated with the TRAC-BF1 code as well. The code does, therefore, predict the boiling two-phase flow in a BWR core even at such flow-decrease event. During the event, differential pressure along each channel between the upper and lower plena decreases by several tens of kPa. The relative perturbations of the differential pressure between both channels, however, remain less than 0.4 %, which is a significantly small amount. In conclusion, the differential pressures between the upper and lower plena of two-parallel channels are, therefore, identical to each other regardless of the power.

元の言語English
ホスト出版物のタイトルProceedings of the 17th International Conference on Nuclear Engineering 2009, ICONE17
ページ625-631
ページ数7
DOI
出版物ステータスPublished - 2009 12 1
外部発表Yes
イベント17th International Conference on Nuclear Engineering, ICONE17 - Brussels, Belgium
継続期間: 2009 7 122009 7 16

出版物シリーズ

名前International Conference on Nuclear Engineering, Proceedings, ICONE
3

Conference

Conference17th International Conference on Nuclear Engineering, ICONE17
Belgium
Brussels
期間09/7/1209/7/16

Fingerprint

Transient analysis
Mass transfer
Two phase flow
Boiling liquids
Void fraction
Heat flux
Time series
Pumps
Recovery
Controllers
Experiments

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

これを引用

Furuya, M., Hara, T., & Mizokami, S. (2009). Transient response of BWR core flow during simulated generator load rejection event. : Proceedings of the 17th International Conference on Nuclear Engineering 2009, ICONE17 (pp. 625-631). (International Conference on Nuclear Engineering, Proceedings, ICONE; 巻数 3). https://doi.org/10.1115/ICONE17-75763

Transient response of BWR core flow during simulated generator load rejection event. / Furuya, Masahiro; Hara, Takashi; Mizokami, Shinya.

Proceedings of the 17th International Conference on Nuclear Engineering 2009, ICONE17. 2009. p. 625-631 (International Conference on Nuclear Engineering, Proceedings, ICONE; 巻 3).

研究成果: Conference contribution

Furuya, M, Hara, T & Mizokami, S 2009, Transient response of BWR core flow during simulated generator load rejection event. : Proceedings of the 17th International Conference on Nuclear Engineering 2009, ICONE17. International Conference on Nuclear Engineering, Proceedings, ICONE, 巻. 3, pp. 625-631, 17th International Conference on Nuclear Engineering, ICONE17, Brussels, Belgium, 09/7/12. https://doi.org/10.1115/ICONE17-75763
Furuya M, Hara T, Mizokami S. Transient response of BWR core flow during simulated generator load rejection event. : Proceedings of the 17th International Conference on Nuclear Engineering 2009, ICONE17. 2009. p. 625-631. (International Conference on Nuclear Engineering, Proceedings, ICONE). https://doi.org/10.1115/ICONE17-75763
Furuya, Masahiro ; Hara, Takashi ; Mizokami, Shinya. / Transient response of BWR core flow during simulated generator load rejection event. Proceedings of the 17th International Conference on Nuclear Engineering 2009, ICONE17. 2009. pp. 625-631 (International Conference on Nuclear Engineering, Proceedings, ICONE).
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