Monitoring the distribution of radionuclides throughout the technological circuits of a nuclear power station

Monitoring of Interloop Density of a Propulsion Nuclear Power System Cooled by Pressurized Water

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Tritium accumulation in the first-loop coolant of a propulsion nuclear power system is examined. The latter method is used for the earliest possible detection of leaky steam generators and for confirmation of the results of instrumentational method of monitoring with a small leak in a steam generator and supplements the first method.Monitoring in an idling regime, using the instrumentational method and laboratory chemical analysis, is impossible because the reference radionuclides 16 N and iodine isotopes have short half lives [3]. 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.

Heat-exchange equipment is potentially dangerous, from the standpoint of interloop leakage, in propulsion nuclear power systems [1].

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“…Monitoring in an idling regime, using the instrumentational method and laboratory chemical analysis, is impossible because the reference radionuclides 16 N and iodine isotopes have short half lives [3]. Monitoring by disassembly and subsequent visual examination of the interior cavities of the steam generators is also impossible because of the circulation of the first-loop coolant in the interpipe space and the structural features of the piping system of the second loop [2].…”