Published May 2009 | Version v1
Miscellaneous

Measurements of Bubbly Flow in a Subchannel by using Optical Sensor Probe

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

Understanding of the two-phase flow structure in a subchannel is extremely important in a view point of the safety analysis in nuclear power plants. The basic characteristic of a two-phase flow is clarified by two parameters such as void fraction and interfacial area concentration. So, extensive analytical and experimental studies have been performed on basic flow channels such as round tube and annulus. But studies on subchannels were very limited because of the geometrical complexity. Recently, experimental studies on a rod bundle have been published. Yun et. al. have been presented the interfacial flow structure of subcooled water boiling flow in a subchannel of a 3x3 rod bundle. Paranjape et. al. have been obtained a flow regime maps for an adiabatic air-water two-phase flow through a flow channel with 8x8 rod bundle. In spite of various experimental efforts to understand the flow structure in a subchannel, there were still coarse and insufficient experimental data. From this circumstance, this study presents precise measurements in a subchannel with a 4x4 rod bundle by using a two sensor optical probe

Part of:
Proceedings of the KNS spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS spring meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2009 spring meeting of the KNS
Dates
18-23 May 2009
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
40099548
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Numerical Data, Non-conventional Literature
Descriptors DEI
BUBBLES; EXPERIMENTAL DATA; FUEL ELEMENT CLUSTERS; NUCLEAR POWER PLANTS; PROBES; SAFETY ANALYSIS; TWO-PHASE FLOW
Descriptors DEC
DATA; FLUID FLOW; FUEL ASSEMBLIES; INFORMATION; NUCLEAR FACILITIES; NUMERICAL DATA; POWER PLANTS; THERMAL POWER PLANTS

Optional Information

Notes
3 refs, 6 figs