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Measurement of the ambient dose equivalent of continuous and average dose rate of pulsed X-ray and gamma radiation in an extremely wide range under harsh operating conditions.

Transmission of units of absorbed dose, directed, individual dose equivalents and their beta radiation power as part of the working standard of absorbed dose (PD) and absorbed dose power (MPD) of beta radiation in a tissue equivalent substance. ▪ Use of closed radionuclide beta radiation sources 90Sr+90Y (BIS-50, 22 GBk), 85Kr (KAC.D3, 15 GBk) and 147Pm (BIP-50, 10 GBk) ▪ Formation of a reference field from sources by a mobile emitter unit using smoothing filters ▪ Source holders with shutter and protective screens ▪ Calibrated length rods and laser device for centering and digitizing ▪ A video surveillance system of readings ▪ The possibility of using an automated extrapolation chamber as part of the installation to reproduce the absorbed dose (absorbed dose rate) of beta radiation in the tissue ▪ Measurement of ionization currents from 1 fA when using an extrapolation chamber and a precision electrometer ▪ Software for installation operation, calibration and calculations ▪ An alarm and blocking system, control of photon radiation levels in the measurement room and operator room

The installation is intended for use in gas-aerosol emission control systems in order to determine the volumetric air flow in ventilation systems by measuring the linear air flow velocity at local points of the dimensional section, as well as for measuring air temperature and humidity at local points. The measuring system of the installation complies with GOST 12.3.018-79 (SSBT. Ventilation systems. Methods of aerodynamic tests).

High sensitivity Audible, light and visual alarm of exceeding the set threshold levels The possibility of using both stationary and wearable versions Automatic recording and storage of at least 10,000 GPS-linked measurement results when using BOI4 The possibility of automatic data transfer to a remote server, as well as processing them in export application software when using BOI4

Purpose: measurement of the volume of air pumped through the analytical filter; measurement of volumetric air flow through an analytical filter. Features: output of information to the LCD indicator; automatic and manual control of an external actuator (valve, crane); obtaining information about the analytical filter used using a barcode reader; transmission of data on the state of the device, the measured volume flow and the pumped volume of air to communication channels; providing access to information via the RS-485 interface; work both independently and as part of radiation monitoring systems

Purpose: measurement of the individual dose equivalent of Hp(10) photon radiation; measurement of the individual dose equivalent of Hp(10) neutron radiation; measurement of the individual dose equivalent in the skin Hp(0.07) and the lens of the eye Hp(3) of photon and beta radiation; measurement of ambient dose equivalent H*(10) of photon radiation.

The principle of operation of dosimeters is based on the accumulation of ionizing radiation energy by detectors proportional to the radiation dose. In DVG-02TM installations, DOZA-TLD complexes, etc., when the detector is heated, the accumulated energy is released in the form of light radiation, which is recorded by an electronic device.

Installation for monitoring radioactive contamination of hands, feet (shoes) and clothing of personnel with alpha- and beta - active substances. Modern and intuitive interface, various versions. Purpose: monitoring the level of contamination of hands, feet (shoes) and clothing of personnel with alpha- and beta-active substances and signaling when exceeding permissible levels; measurement of alpha and beta radiation flux density from the surface of the hands, feet (shoes) and clothing of personnel; measurement of the surface activity of alpha- and beta-emitting radionuclides of hands, feet (shoes) and clothing of personnel.

Purpose: measurement of individual dose equivalent (IED) of mixed gamma-neutron radiation; measurement of individual dose equivalent (IED) of neutron radiation;

X–ray radiation dosimeters clinical DRC, depending on the modification, are designed for: measuring the product of the kerma (absorbed dose) in the air by the cross-sectional area of the X-ray beam (hereinafter referred to as the product of the kerma in the air by the area) when using the DRC-1, DRC-1E, DRC-1M Outline, DRC-1M dosimeters with the DRC measuring console-1M-E03, DRC-1M-E04, DRC-1M-E05, DRC-1M-E06; measurements of the product of the kerma power (absorbed dose) in the air per area (hereinafter referred to as the product of the kerma power in the air per area) using the DRK–1E and DRK-1M dosimeters equipped with the DRK-1M-E06 measuring console; measurements of the product of the kerma (absorbed dose) in the air along the length (hereinafter referred to as the product of the kerma in the air along the length) using DRK-1M-CT dosimeters; measurements of kerma (absorbed dose) in the air; measurements of the kerma power (absorbed dose) in the air when using DRK-1M dosimeters.