Published May 1979
| Version v1
Report
Investigation of post-CHF heat transfer for water-cooled reactor application and development of two-phase flow instrumentation
- 1. Lehigh Univ., Bethlehem, PA
Description
A two-phase loop has been modified to obtain post-CHF heat transfer data with water at system pressures up to 100 psia. Development of a probe to measure non-equilibrium vapor superheat is in progress. A suitable test section for obtaining post-CHF data which will incorporate measurement of vapor superheat is in the design stage. A concept for measuring liquid film thickness in two phase flow has been developed and tested with reasonable success. Optimization of probe geometry is in progress. A suitable method for measuring film velocities is being sought. Present investigation is directed towards the use of hydrogen bubbles as tracers
Additional details
Publishing Information
- Imprint Title
- Review group meeting on two-phase flow instrumentation
- Journal Page Range
- p. I.10.1-I.1.14.
- Report number
- NUREG/CP--0006
Conference
- Title
- Two-phase instrumentation review meeting.
- Dates
- 13 - 14 Mar 1978.
- Place
- Troy, NY, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11499788
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BLOWDOWN; CRITICAL HEAT FLUX; FLOWMETERS; MEASURING INSTRUMENTS; PERFORMANCE TESTING; PROBES; SPECIFICATIONS; TWO-PHASE FLOW; WATER COOLED REACTORS
- Descriptors DEC
- FLUID FLOW; HEAT FLUX; REACTORS; TESTING