Actions for Measurements and calculations of water velocity, momentum flux, and related flow parameters obtaned from single-phase water integral acceptance tests of the PKL instrumented spool pieces
Measurements and calculations of water velocity, momentum flux, and related flow parameters obtaned from single-phase water integral acceptance tests of the PKL instrumented spool pieces
- Author
- Stein, W.
- Published
- United States : [publisher not identified], 1979.
Springfield, Va. : National Technical Information Service, [approximately 1979] - Physical Description
- microfiche : negative ; 11 x 15 cm
- Summary
- The operation of the emergency core cooling system and its related steam-binding problems in pressurized water reactors is the subject of a cooperative study by the United States, Germany, and Japan. Lawrence Livermore Laboratory and EG and G, Inc., San Ramon Operations, are responsible for the design, hardware, and software of the 80.8-mm and 113-mm spool piece measurement systems for the German Primarkreislauf (PKL) Test Facility at Kraftwerk Union in Erlangen, West Germany. This work was done for the US Nuclear Regulatory Commission, Division of Reactor Safety Research, under its 3-D Technical Support and Instrumentation Program. Four instrumented spools capable of measuring individual phase parameters in two-phase flows were constructed. Each spool contains a flow turbine, drag screen, three-beam densitometer, and pressure and temperature probes. A computerized data acquisition system is also provided to store and analyze data from the four spools. The four spools were shipped to the PKL Test Facility in West Germany for acceptance testing in a water-flow loop. Spool measurements of velocity and momentum flux were compared to the values obtained from an orifice meter installed in the loop piping system. The turbine flowmeter velocity data for all tests were within allowable tolerances. Drag screen momentum flux measurements were also within tolerance with the exception of a few points.
- Report Numbers
- UCRL-52855
- Other Subject(s)
- 21 specific nuclear reactors and associated plants
- 210200 - power reactors, nonbreeding, light-water moderated, nonboiling water cooled
- 22 general studies of nuclear reactors
- 220900 - nuclear reactor technology- reactor safety
- Coolant loops
- Cooling systems
- Eccs
- Engineered safety systems
- Flowmeters
- Fluid flow
- Liquid flow
- Measuring instruments
- Performance testing
- Pwr type reactors
- Reactor protection systems
- Reactors
- Test facilities
- Testing
- Two-phase flow
- Water cooled reactors
- Water moderated reactors
- Collection
- NTIS collection.
- Note
- DOE contract number: W-7405-ENG-48
OSTI Identifier 5928687
Research organization: Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States).
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