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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.

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 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.

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.

Purpose determination of the effective dose of patients in radiation diagnostics; control of stability of parameters of X-ray machines

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

Measurement of the power of the ambient dose equivalent and the ambient dose equivalent of neutron radiation, as well as simultaneous monitoring of the power of the ambient dose equivalent and the ambient dose equivalent of gamma radiation. A wide energy range 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 Audible and visual alarm of exceeding threshold levels

- Measurement of the dose and power of the ambient equivalent of the dose of X-ray and gamma radiation; - Control of the content of 137Cs in samples placed in a Marinelli vessel with a volume of 0.5 liters, both with and without the protection unit (BZ); - Measurement of the flux density of alpha and beta particles from contaminated surfaces (external detection unit BDPS-02); - Search and detection of X-ray and gamma radiation sources. High sensitivity Spectrum display mode when connected to a PC

Depending on the set of detection units, the device is designed to measure: - ambient dose equivalent and ambient dose equivalent power of X-ray, gamma and neutron radiation; - kerma and kerma power in the air; - the directional dose equivalent and the power of the directional dose equivalent of continuous X-ray and gamma radiation; - the flux and fluence densities of alpha and beta particles from contaminated surfaces; - the flux and fluence densities of neutron radiation with a known energy distribution; - surface activity and number of decays of 239Pu and 90Sr + 90Y; - operational search for sources of ionizing radiation and radioactive materials.