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