Doza

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 verification and calibration of individual beta radiation dosimeters. Properties The unit transmits units of absorbed dose (PD) and absorbed dose rate (MPD) of beta radiation in a tissue equivalent substance at a depth corresponding to a surface density of 7 mg•cm-2; the transition to units of the individual equivalent of the Hp dose (0.07) in sieverts from units of beta radiation absorbed in the tissue in gray is carried out using conversion coefficients recommended by the international standard ISO 6980-3:2006; the installation can be used in metrological bodies for verification of individual beta radiation dosimeters such as DMC 2000 XB, EPD Mk2 and others.

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.

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.

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.

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

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).

Dosimeter is a gamma-beta radiation radiometer for working in "dirty" conditions. Allows you to switch modes and take measurements in conditions of radioactive contamination. Measurement of the beta radiation flux density is carried out with automatic subtraction of the gamma radiation background. Purpose: measurement of the ambient dose equivalent of H*(10) gamma radiation; measurement of ambient dose equivalent of H*(10) gamma radiation; measurement of beta particle flux density; estimation of the counting rate with combined measurements of gamma and beta radiation.