Doza

Purpose: measurement of the product of the air kerma by length, followed by the calculation of the CTDI tomographic dose index (using the CTDI phantom) for the following calculation of the effective dose received by the patient; monitoring the stability of medical X-ray machines during their operation; calculation of the dose index of a computer tomograph (MPCT) according to GOST R IEC 61223-2-6-2001.

Purpose: measurement of individual dose equivalent (IED); measurement of the power of the individual dose equivalent (MIED).

Purpose: processing of information received from detection units (primary converters); data transmission to the information network; data transfer to a portable computer (remote control tuning PN-PC); storage of threshold settings and parameters of detection units (primary converters); power supply and diagnostics of detection units (primary converters); output of threshold exceeding signals to built-in sound and LED alarms and to remote alarm units (BAS/BAS-1c); output of discrete signals (dry contacts); archiving of data in non-volatile memory.

The fast-deployable radiation monitoring system (BR ASKRO) is intended for the operational creation of a local autonomous automated network of portable radiation monitoring posts in places where radiation emergencies occur. The main purpose of the system being created is continuous radiation monitoring, on areas up to 1 km2, when performing work to localize accidents and eliminate their consequences to ensure the safe operation of personnel of emergency rescue units, as well as to monitor the effectiveness of the work performed.

The installation provides determination of volumetric activities of gamma-emitting radionuclides in various technological media (for example, liquids, pulps and vapors in pipes) and transmission of spectrometric information over a local network. Purpose: measurement of the volumetric activity of gamma-emitting radionuclides in technological environments; identification of leaky steam generators and monitoring of the volumetric activity of gamma-emitting radionuclides in the acute steam of the second circuit of nuclear power plants (VVR-440, 1000) according to the control method developed by VNIIAES.

Checking the performance of cardiographs, cardiac monitors and cardiac units of intensive care monitors; checking the general functionality and imitation of the patient (when checking stress systems, a cardioid signal is formed); checking the amplitude of the signal recording (a U-shaped signal is formed).

Purpose: to provide bidirectional data exchange with individual dosimeters DKG-05D, DVS-02D.

Appointment: Measurement of the ambient dose equivalent (MAED) power of gamma radiation during radiation reconnaissance and operational control of radioactive contamination of the area. Installations can be installed on cars and other mobile means, except for air.

The mobile spectrometric installation MKG-01D is designed to measure the energy spectrum of gamma radiation and is used to determine the isotopic composition and specific activity of gamma-emitting radionuclides of radioactive waste (RW) in light-duty containers of various shapes and geometries (metal barrels, plastic containers), in non-returnable protective reinforced concrete containers of the NPC type, as well as to determine activity of extended objects. Purpose: implementation of a fully automated system designed to measure, process and present spectrometric information about the sources of controlled gamma radiation

Sorption analytical filters AFA-SI are used for simultaneous capture and determination of samples of aerosols and vapors of radioactive iodine, followed by measurement of the delayed sediment by radiometric devices.

Purpose measurement of the ambient dose equivalent of N*(10) gamma radiation; measurement of ambient dose equivalent of H*(10) gamma radiation; assessment of surface contamination with radionuclides.

Purpose: measuring the level of contamination of hands, feet (shoes) and clothing of personnel with beta-active substances and signaling when exceeding permissible levels monitoring the level of contamination with alpha-emitting radionuclides monitoring the contamination of personnel at nuclear power plants, nuclear fuel cycle enterprises (NFC), radiological laboratories, other enterprises and institutions using radioactive substances.