METHOD FOR CHECKING PRIMARY-CIRCUIT EQUIPMENT OF SHIPBOARD WATER-COOLED NUCLEAR POWER PLANT FOR TIGHTNESS IN THE COURSE OF HYDRAULIC TESTS Russian patent published in 2006 - IPC G21C17/07 

FIELD: shipboard nuclear power plants.

SUBSTANCE: proposed method includes measurement of reference radionuclide-tritium content and calculation of primary coolant leakage. This method is characterized is that air space between primary-circuit equipment and reactor vessel is sealed for locating leaky points. To this end air filled space or hood is organized above suspected point of coolant leakage. Damp air samples are taken from insulated air space and specific activity of reference radionuclide-tritium in damp air is measured, then volumetric activity of tritium in insulated space is calculated up to pressure rise and after its drop within reactor.

EFFECT: facilitated check of flanged joints between primary-circuit equipment and reactor vessel for tightness during hydraulic tests.

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