Time-resolved measurement of subchannel void distribution for boiling two-phase flow in 5 x 5 rod bundle at high-pressure and high-temperature

Conference · Fri Jul 01 04:00:00 EDT 2016

OSTI ID:22977495

Arai, Takahiro; Furuya, Masahiro; Shirakawa, Kenetsu; Nishi, Yoshihisa ^[1]

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1. Central Research Institute of Electric Power Industry 2-11-1 Iwado-kita, Komae-shi, Tokyo 201-8511 (Japan)

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. (authors)

• Research Organization: American Nuclear Society - ANS, Thermal Hydraulics Division, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 22977495
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
42 ENGINEERING
BOILING
BWR TYPE REACTORS
ELECTRODES
FLUID MECHANICS
FUEL ELEMENT CLUSTERS
FUEL STORAGE POOLS
REACTOR CORES
RODS
SENSORS
SPENT FUELS
TEMPERATURE DISTRIBUTION
THERMOCOUPLES
TWO-PHASE FLOW
VOID FRACTION
VOIDS