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

Masahiro Furuya, Takashi Hara, Shinya Mizokami

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

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.

Original languageEnglish
Title of host publicationProceedings of the 17th International Conference on Nuclear Engineering 2009, ICONE17
Pages625-631
Number of pages7
DOIs
Publication statusPublished - 2009 Dec 1
Externally publishedYes
Event17th International Conference on Nuclear Engineering, ICONE17 - Brussels, Belgium
Duration: 2009 Jul 122009 Jul 16

Publication series

NameInternational Conference on Nuclear Engineering, Proceedings, ICONE
Volume3

Conference

Conference17th International Conference on Nuclear Engineering, ICONE17
CountryBelgium
CityBrussels
Period09/7/1209/7/16

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

Cite this

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

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Furuya, M, Hara, T & Mizokami, S 2009, Transient response of BWR core flow during simulated generator load rejection event. in Proceedings of the 17th International Conference on Nuclear Engineering 2009, ICONE17. International Conference on Nuclear Engineering, Proceedings, ICONE, vol. 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. In 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).
@inproceedings{fc8c46dc75104e4d8828d5899940797e,
title = "Transient response of BWR core flow during simulated generator load rejection event",
abstract = "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.",
author = "Masahiro Furuya and Takashi Hara and Shinya Mizokami",
year = "2009",
month = "12",
day = "1",
doi = "10.1115/ICONE17-75763",
language = "English",
isbn = "9780791843536",
series = "International Conference on Nuclear Engineering, Proceedings, ICONE",
pages = "625--631",
booktitle = "Proceedings of the 17th International Conference on Nuclear Engineering 2009, ICONE17",

}

TY - GEN

T1 - Transient response of BWR core flow during simulated generator load rejection event

AU - Furuya, Masahiro

AU - Hara, Takashi

AU - Mizokami, Shinya

PY - 2009/12/1

Y1 - 2009/12/1

N2 - 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.

AB - 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.

UR - http://www.scopus.com/inward/record.url?scp=77952873985&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=77952873985&partnerID=8YFLogxK

U2 - 10.1115/ICONE17-75763

DO - 10.1115/ICONE17-75763

M3 - Conference contribution

SN - 9780791843536

T3 - International Conference on Nuclear Engineering, Proceedings, ICONE

SP - 625

EP - 631

BT - Proceedings of the 17th International Conference on Nuclear Engineering 2009, ICONE17

ER -