Category Archives: Natural circulation data and methods for advanced water cooled nuclear power plant designs

Full pressure core make-up tank test

Passive core make-up water tank is used so as to eliminate high pressure safety injection pumps. Transient characteristic research of core make-up water tank in the case of small LOCA were performed. The break sizes are: 2, 6, 12, 18, 30 mm respectively. Thermal hydraulic behaviors of pressurizer and draining flow rate measurement from core make-up water tank to primary […]

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. Single-Phase NC (SPNC)

SPNC regime implies no void occurrence in the upper plenum of the system. Therefore, coolant at the core outlet shall be subcooled up to nearly saturated. Core flowrate derives from the balance between driving and resistant forces. Driving forces are the result of fluid density differences occurring between [descending side of U-Tubes & vessel downcomer] and [core & ascending side […]

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Nonuniform diameter loops (NDLs)

Most practical applications of natural circulation employ non-uniform diameter loops. Common examples are the nuclear reactor loop, solar water heater, etc. Most test facilities simulating nuclear reactor loops also use non-uniform diameter loops. Depending on the operating pressure, the non-uniform diameter loops can be categorised as High pressure loops and Low pressure loops. Most studies are conducted in the high-pressure […]

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E. F. Hicken, H. Jaegers

Institute for Safety Research and Reactor Technology, Forschungszentrum Julich A. Schaffrath, F.-P. Weiss Institute for Safety Research, Forschungszentrum Rossendorf Germany Abstract. For the study of the effectiveness of passive safety systems a high pressure (up to 7 MPa) and high power (up to 4 MW) test facility — named NOKO — has been constructed and operated at the Forschungszentrum Julich. […]

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