Abstract
A subchannel void sensor (SCVS) was improved to acquire time-resolve boiling two-phase flow in a 5-by-5 heated rod bundle at high-pressure and high-temperature. The SCVS consists of 6-by-6 wire electrodes and 5-by-5 rod electrodes. The SCVS can acquire a time series data of local void fraction at 32 points of central subchannel region in addition to 100 points of rod surface regions between rods. The devised sensors are installed in the heated rod bundle at eight height levels to acquire two-phase flow dynamics and its development. The axial and radial power profile of the heated rod bundle are uniform, and eight pairs of sheath thermocouples are embedded on the heated rod to monitor its surface temperature distribution. The paper addresses the axial and cross-sectional distributions of void fraction at various pressure and rod bundle power conditions, which simulates an accidental condition in reactor core and in a spent fuel pool of a boiling water reactor (BWR). The experimental data are suitable to validate the computational multi-fluid dynamics (CMFD) and subchannel codes.
| Original language | English |
|---|---|
| Title of host publication | International Topical Meeting on Advances in Thermal Hydraulics 2016, ATH 2016 |
| Publisher | American Nuclear Society |
| Pages | 193-200 |
| Number of pages | 8 |
| ISBN (Electronic) | 9780894487330 |
| Publication status | Published - 2016 Jan 1 |
| Externally published | Yes |
| Event | 3rd International Topical Meeting on Advances in Thermal Hydraulics 2016, ATH 2016 - New Orleans, United States Duration: 2016 Jun 12 → 2016 Jun 16 |
Publication series
| Name | International Topical Meeting on Advances in Thermal Hydraulics 2016, ATH 2016 |
|---|
Conference
| Conference | 3rd International Topical Meeting on Advances in Thermal Hydraulics 2016, ATH 2016 |
|---|---|
| Country | United States |
| City | New Orleans |
| Period | 16/6/12 → 16/6/16 |
Fingerprint
Keywords
- Boiling two-phase flow
- High pressure
- Rod bundle
- Subchannel void sensor
- Void fraction
ASJC Scopus subject areas
- Nuclear Energy and Engineering
- Geotechnical Engineering and Engineering Geology
- Nuclear and High Energy Physics
Cite this
Time-resolved measurement of subchannel void distribution for boiling two-phase flow in 5x5 rod bundle at high-pressure and high-temperature. / Arai, Takahiro; Furuya, Masahiro; Shirakawa, Kenetsu; Nishi, Yoshihisa.
International Topical Meeting on Advances in Thermal Hydraulics 2016, ATH 2016. American Nuclear Society, 2016. p. 193-200 (International Topical Meeting on Advances in Thermal Hydraulics 2016, ATH 2016).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution
}
TY - GEN
T1 - Time-resolved measurement of subchannel void distribution for boiling two-phase flow in 5x5 rod bundle at high-pressure and high-temperature
AU - Arai, Takahiro
AU - Furuya, Masahiro
AU - Shirakawa, Kenetsu
AU - Nishi, Yoshihisa
PY - 2016/1/1
Y1 - 2016/1/1
N2 - A subchannel void sensor (SCVS) was improved to acquire time-resolve boiling two-phase flow in a 5-by-5 heated rod bundle at high-pressure and high-temperature. The SCVS consists of 6-by-6 wire electrodes and 5-by-5 rod electrodes. The SCVS can acquire a time series data of local void fraction at 32 points of central subchannel region in addition to 100 points of rod surface regions between rods. The devised sensors are installed in the heated rod bundle at eight height levels to acquire two-phase flow dynamics and its development. The axial and radial power profile of the heated rod bundle are uniform, and eight pairs of sheath thermocouples are embedded on the heated rod to monitor its surface temperature distribution. The paper addresses the axial and cross-sectional distributions of void fraction at various pressure and rod bundle power conditions, which simulates an accidental condition in reactor core and in a spent fuel pool of a boiling water reactor (BWR). The experimental data are suitable to validate the computational multi-fluid dynamics (CMFD) and subchannel codes.
AB - A subchannel void sensor (SCVS) was improved to acquire time-resolve boiling two-phase flow in a 5-by-5 heated rod bundle at high-pressure and high-temperature. The SCVS consists of 6-by-6 wire electrodes and 5-by-5 rod electrodes. The SCVS can acquire a time series data of local void fraction at 32 points of central subchannel region in addition to 100 points of rod surface regions between rods. The devised sensors are installed in the heated rod bundle at eight height levels to acquire two-phase flow dynamics and its development. The axial and radial power profile of the heated rod bundle are uniform, and eight pairs of sheath thermocouples are embedded on the heated rod to monitor its surface temperature distribution. The paper addresses the axial and cross-sectional distributions of void fraction at various pressure and rod bundle power conditions, which simulates an accidental condition in reactor core and in a spent fuel pool of a boiling water reactor (BWR). The experimental data are suitable to validate the computational multi-fluid dynamics (CMFD) and subchannel codes.
KW - Boiling two-phase flow
KW - High pressure
KW - Rod bundle
KW - Subchannel void sensor
KW - Void fraction
UR - http://www.scopus.com/inward/record.url?scp=84992044488&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=84992044488&partnerID=8YFLogxK
M3 - Conference contribution
AN - SCOPUS:84992044488
T3 - International Topical Meeting on Advances in Thermal Hydraulics 2016, ATH 2016
SP - 193
EP - 200
BT - International Topical Meeting on Advances in Thermal Hydraulics 2016, ATH 2016
PB - American Nuclear Society
ER -