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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)

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

Control of individual radiation doses from X-ray and gamma radiation. Together with the reader and software, they form an effective system for automated control of dose loads on personnel. ▪ Simultaneous measurement of the power of the individual dose equivalent and the dose of gamma radiation ▪ Automatic compensation of the detector's own background ▪ The mode of signaling the presence of pulsed radiation with a duration of 10 ns (optional)

A small-sized economical device for measuring the power of the ambient dose equivalent and the ambient dose equivalent of X-ray and gamma radiation. A unique combination of economy, speed and usability Working time without replacing batteries (2 x AA): AT2140 - 5000 hours, AT2140A, A/1 - 10000 hours Search mode USB interface and software for configuring the dosimeter and viewing the measured information (AT2140A/1)

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

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.

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 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.

Control of individual radiation doses from X-ray and gamma radiation. Together with a reader connected to a PC and specialized application software, they form an effective system for automated control of dose loads on personnel. Silicon Planar Detector Lack of own background Simultaneous measurement of dose loads on internal organs Hp(10) and skin Hp (0.07)

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) of mixed gamma-neutron radiation; measurement of individual dose equivalent (IED) of neutron radiation;