FIELD: technological processes.
SUBSTANCE: group of inventions relates to the technology of handling high-activity solutions and can be used, for example, as part of a complex of control means for design and beyond-design-basis accidents at nuclear power plants to obtain additional information on the nature of reactor core damage based on radiochemical and chemical analysis results in laboratory conditions of composition of selected samples of aqueous media from processing lines and equipment of power unit. According to the proposed method, the path is spilled, the sample is degassed, the degassed sample is directed into the main pipeline for its dilution in automatic mode with the specified dilution ratio with subsequent extraction of the diluted sample and washing of the path. Before main pipeline is pumped, initial medium is cooled down and pressure is reduced to atmospheric pressure. Simultaneously with sample degassing it is cleaned from suspended particles. Flushing of the main pipeline is carried out until equilibrium conditions of sampling are determined, determined by stabilizing dose rate measured at the outlet of the path. Main pipeline contains calibrated sections of design volume, which provide required multiplicity of sample dilution. Sample is diluted with specified volume of diluent by its displacement from selected calibrated section into mixing chamber. Selection of the calibrated section, as well as the washing termination process, are performed at stabilization of the dose rate measured at the output of the path. To estimate the actual dilution rate of the sample, said path is periodically calibrated.
EFFECT: assurance of representative nature of the sample as per the expanded list of radionuclide and chemical composition of water medium, dissolved gases and solid-phase particles with evaluation of their granulometric composition.
11 cl, 2 dwg
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Authors
Dates
2019-09-03—Published
2019-03-04—Filed