Atomtekh

Building a flexible and reliable multi-channel system Independent measurements on each channel in a wide range of gamma and neutron radiation dose rates and neutron and beta particle flux densities Audiable and light alarms High reliability and self-control Software that allows you to display on the PC monitor the current radiation situation in the controlled area Data logging Backup power supply The possibility of integration with external security systems

▪ Measurements without sampling in geometry 4π ▪ Intelligent detection unit in an airtight container ▪ The possibility of further detailed processing of the measured data using specialized software

Gamma radiation Detection Units (BDKG-04, BDKG-22, BDKG-23, BDKG-23/1, BDKG-24, BDKG-25, BDKG-30, BDKG-32, BDKG-35, BDKG-36, BDKG-38, BDKG-204, BDKG-224, BDKG-230) are designed to use as part of stationary and mobile radiation monitoring posts and robotic devices for ground, aviation and marine applications.

Rapid assessment of surface contamination with alpha-active radionuclides, in particular, polonium-210. The device is easy to operate, suitable for use by personnel of any qualification, including at home. ▪ Scintillation detector ▪ Silicon photoelectronic multiplier ▪ High sensitivity ▪ Light and sound indication when registering alpha particles ▪ Long-term operation without recharging ▪ 1" OLED colour screen

- Measurement of pollution density and specific activity of radionuclides 134Cs and 137Cs in soils and soils; - Measurement of the specific activity of radionuclides 137Cs, 134Cs, 131I in water, food, forestry products, agro-industrial complex and liquid radioactive waste; - Determination of the content of natural radionuclides 40K, 226Ra, 232Th; - Identification of radionuclides: 134Cs, 137Cs, 131I, 40K, 226Ra, 232Th; - Measurement of the ambient dose equivalent of gamma radiation Measurements without sampling with GPS-binding Intelligent detection unit in an airtight container Automatic determination of the thickness of the contaminated soil layer by radionuclides 137Cs and 134Cs

- 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.

Determination of the position of the detection device in space during measurements A cable coil with current transfer Presentation of measurement results in the form of distribution maps of the content of controlled radionuclides or the dose rate of gamma radiation Expert mode for the analysis of the instrument spectrum with automatic identification of the radionuclide composition of the sample GARM expert software for subsequent data processing and analysis, as well as radiation mapping

Displaying the spectra and dose rates measured by each detection unit (DB) on the object plan or terrain map Identification of the radionuclide composition of the source The possibility of expanding the energy range up to 5 MeV Sealed DB design (IP68) Backup power supply

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

The result of determining the energy distribution of the neutron radiation flux density is used to calculate such quantities as: - integral neutron flux density; - the average energy of neutron radiation in the spectrum; - the average neutron radiation energy by dose; - dose equivalent per unit flow density; - dose equivalent; - effective dose. ▪ Methodological support of measurements ▪ It is possible to supply an expanded set of polyethylene retarder spheres with diameters: 3,5”; 4,5”; 5”; 7”; 9”; 9,5”

Measurements in wide ranges of capacities doses and energies Measurement of dose rate and duration of exposure during short-term radiation from 0.03 s Measurement of the average dose rate of pulsed radiation with a pulse duration of 10 ns (AT1123) The possibility of remote measurements using a remote control The possibility of stationary location with external audible and visual alarms with "dry" contacts for controlling actuators The possibility to connect to a PC for organizing a continuous monitoring system with a documentation function