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A high-precision dosimeter with extensive functionality: measurement of DC power, electric charge, charge by numerical integration of current, kerma and kerma power in the air, kerma by numerical integration of kerma power and other radiological quantities. Composition of the dosimeter: - Electrometric measuring unit (electrometer) - PTW-Freiburg ionization chambers (Germany) to choose from: TM23342 Flat-parallel X-ray (volume 0.02 cm3) TM31010 Cylindrical (volume 0.125 cm3) TM30010 Thimble (volume 0.6 cm3) TM23361 Cylindrical (volume 30 cm3) TM32002 Spherical (volume 1000 cm3)

Measures: - the power of the absorbed dose of gamma radiation in a tissue equivalent substance with radiation thickness of 1 g/cm2; - contamination of surfaces with beta-nuclides (beta radiation flux density): in the energy range from 0.08 to 3.0 MeV in the energy range from 0.3 to 3.0 MeV Measurement of radioactive emissions: - in the measurement ranges of absorbed dose rate: - with the BDZS-10S detection unit; - without the BDZS-10S detection unit; - in the range of measuring the beta radiation flux density with the BDZS-10S detection unit from 10 mkrad/h to 999 rad/h from 10 mrad/h to 999 rad/h 10...999·102 parts/cm2min The meter is resistant to the background of gamma radiation from the 137Cs source when measuring the contamination of surfaces with beta-active substances, depending on the measurement ranges: from 10 to 102 parts/cm2min: absorbed dose rate is no more than 0.1 mrad/h from 102 to 103 parts/cm2min: absorbed dose rate is no more than 1.0 mrad/h from 103 to 104 parts/cm2min: absorbed dose rate is no more than 10.0 mrad/h from 104 to 105 parts/cm2·min: absorbed dose rate is no more than 100 mrad/h Limits of permissible basic error: - when measuring the absorbed dose rate of gamma radiation under normal climatic conditions from a second-class caesium-137 source relative to the measured value with a confidence probability of 0.95: the permissible basic error does not exceed ± 20% (at release) and ± 25% (during operation) - when measuring the absorbed dose rate of gamma radiation from 10 to 100 mrad/h under normal climatic conditions using a second-class caesium-137 source with a measuring console UI-177S without using BDZS-10C relative to the measured value with a confidence probability of 0.95: the permissible basic error does not exceed ± 20% (at release) and ± 25% (during operation) - when measuring the beta radiation flux density under normal climatic conditions from a second-digit strontium-90 + yttrium-90 source relative to the measured value with a confidence probability of 0.95: the permissible basic error does not exceed ± 20% (at release) and ± 25% (during operation) The mass of the meter is no more than 3.76 kg

Purpose: measurement of the product of the air kerma by length, followed by the calculation of the CTDI tomographic dose index (using the CTDI phantom) for the following calculation of the effective dose received by the patient; monitoring the stability of medical X-ray machines during their operation; calculation of the dose index of a computer tomograph (MPCT) according to GOST R IEC 61223-2-6-2001.

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.

A simple and reliable device for monitoring the radiation situation in rooms where work is carried out with radioactive sources (substances, medications, installations). If the set threshold value of the dose rate is exceeded, the device gives a sound and light signal, controls external devices (for example, door locking devices). Purpose: measurement of the ambient dose equivalent of gamma radiation (MAED); sound and light alarm about exceeding the set threshold; activation of external signaling or actuating devices.

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

Sorption analytical filters AFA-SI are used for simultaneous capture and determination of samples of aerosols and vapors of radioactive iodine, followed by measurement of the delayed sediment by radiometric devices.

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 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.

- Search and detection of gamma radiation sources with identification of radionuclide composition - Measurement of the ambient dose equivalent of gamma radiation The combination of compactness and high sensitivity The possibility to analyze the spectrum and identify radionuclides without using a PC A built-in GPS module Audiable, light and vibration alarms

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").

Detection of gamma and neutron radiation sources in the flow of pedestrians crossing the border of the controlled object. 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 High reliability and self-control Backup power supply At the request of the user, the MCI can be supplied without a neutron channel.