MONITORING OF INTERLOOP DENSITY OF A PROPULSION NUCLEAR POWER SYSTEM COOLED BY PRESSURIZED WATER

摘要

Tritium accumulation in the first-loop coolant of a propulsion nuclear power system is examined. The results confirm that tritium can be used as a reference radionuclide for monitoring interloop density. The sensitivity of the radiometric method of tritium monitoring for determining coolant leakage in the first loop during operation of the power system at power and in an idling regime is estimated.