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Deliveries in the CIS are carried out by LLC NPP RADIKO 249035, Kaluga region, Obninsk, Marx Avenue, 14 Phone: 8(48439) 4-97-16, 4-97-18 / Fax: 8(48439) 4-97-68 E-mail: main@radico.ru / Web site: http://www.radico.ru Control of exceeding the threshold value of the total activity of radionuclides 51Cr, 54Mn, 58Co, 59Fe, 65Zn, 95Nb, 100mAg, 103Ru, 124Sb, 141Ce, 144Ce in the lungs; Flexible software control of the spectrometer functions, the formation of a database and a report on the results of the survey Express control capacity - 15 people per hour The possibility of sharing AT1316(AT1316A) and AT1322(AT1322/1) The possibility of accommodation in a minibus as part of a mobile radiation control laboratory

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

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

- 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.

The drip collector is designed to remove droplet moisture when sampling air from indoor ventilation systems and is installed in gas aerosol sampling systems. Purpose: removal of droplet moisture from the selected air sample; accumulation of droplet moisture; indication of the level of accumulated moisture; draining the accumulated moisture.

Logging data on dose rate levels and exceeding threshold levels The possibility of placing the detection unit and the temperature sensor at a distance of up to 1 km separately from the scoreboard Additional protection from direct exposure to precipitation

Gamma radiation detection units (BDKG-05M, BDKG-11M, BDKG-19M, BDKG-201M, BDKG-203M, BDKG-205M, BDKG-211M, BDKG-219M) for use as part of stationary and mobile radiation monitoring posts and robotic devices for ground, aviation and marine applications

A low-background alpha-beta radiometer with a silicon detector, widely used for measuring small activities. It is recommended for measuring the total alpha and beta activity of natural and drinking waters, as well as for measuring the activity of alpha-emitting radionuclides by spectrometric method. Purpose: measurement of the total activity of alpha-emitting nuclides in "thick" and "thin" counting samples of environmental objects; measurement of the total activity of beta-emitting nuclides in counting samples of soil samples, water samples, air filters and samples obtained by selective radiochemical extraction; measurement of alpha activity of nuclides in counting samples obtained after radiochemical preparation by radiometric method (if available); measurement of alpha activity of nuclides in counting samples obtained after radiochemical preparation by the spectrometric method (if there are techniques and a set of spectrometric "UMF - Spectrum").

Installation for continuous automatic monitoring of the concentration of radioactive aerosols in autonomous mode or as part of automatic radiation monitoring systems in the air of working rooms and ventilation systems. Purpose: measurement of the volumetric activity of alpha-emitting radionuclides and beta-emitting radionuclides contained in the form of aerosols in the air.

Rapid adaptation to changes in the radiation background Audible and light alarms The possibility to create a network of MCI (up to 32) under the control of a PC and specialized software Mobility and the possibility to organize the control of passages in a short time High reliability and self-control Backup power supply