Measuring dynamic displacement inside a reactor pressure vessel at 310°C and 110 bar
In a research project sponsored by the West German Government, critical components of light-water nuclear reactors are being rigidly tested.
In a research project sponsored by the West German Government, critical components of light-water nuclear reactors are being rigidly tested. One series of tests simulates a rupture in the primary-coolant circuit and measures the effect of resulting loads on the reactor pressure vessel and its internals. The displacement transducers used in the test are capable of very precise measurement despite extraordinarily high pressure and temperature conditions inside the pressure vessel.
Auteur : Werner Zirnig, Klemens Meuer
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