Search

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

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.

Measures: - absorbed dose rate of gamma radiation in a tissue equivalent substance with a radiation thickness of 1 g/cm2 in the energy range from 0.08 to 3.0 MeV Measurement ranges of the absorbed dose rate of gamma radiation: - from 10 to 100 mkrad/h ("Beta-1" type counter); - from 0.1 to 100 mrad/h ("Beta-1" type counter); - from 100 to 1000 mrad/h ("SI3BG" type counter); - from 1.0-10 rad/h ("SI3BG" type counter); - from 10-999 rad/h ("SI3BG" type counter); - from 10 mkrad/h to 999 rad/h Measurement time: - in the measurement ranges of the absorbed dose rate , "Beta-1" type counter: - from 10 to 100 mkrad/h: no more than 50 sec.; - from 0.1 to 1.0 mrad/h: no more than 25 sec.; - from 1.0 to 10 mrad/h: no more than 12.5 sec.; - from 10 to 100 mrad/h: no more than 3 sec.; - in the measurement ranges of the absorbed dose rate, "SI3BG" type counter: - from 100 to 1000 mrad/h: no more than 6 sec.; - from 1.0 to 10 rad/h: no more than 3 sec.; - in the measurement ranges of the absorbed dose rate, "SI3BG" type counter: - from 10 to 999 rad/h: no more than 3 sec. Power consumed by the meter: - when powered by AC power: no more than 5 VA  - when powered by a rechargeable battery: no more than 5 watts The warranty period of operation from the date of commissioning of the meter within the warranty period of storage: 2 years. Warranty obligations comply with GOST standard B15.306 The weight of the meter is 4.4 kg

The field of fast and thermal neutrons in a collimated beam Fast neutron field in “open” geometry using a screening cone according to ISO 8529-2 Drum source magazine with polyethylene and concrete protection at a depth of 1 meter Software control of the movement of sources and positioning of the mobile platform An alarm and blocking systems, radiation monitoring Control from the operator panel or computer with verification automation functions

Detection of SCR in all possible range of its characteristics High reliability Self-monitoring of components Backup power supply Recording and storage of measurement results in the non-volatile memory of the device The possibility of integration with external security systems DRG-AT2331 together with SRK-AT2327, personal computer and software "SARK.NET " allows you to form an alarm system for detecting the occurrence of a self-sustaining chain reaction (SAS SCR).

Modular principle of system construction Automatic correction of threshold levels when the background level of the environment changes High reliability and self-control Backup power supply Automatic data logging The possibility of connecting a video surveillance system

Logging data on dose rate levels and exceeding threshold levels Software that allows you to display on a PC monitor the current radiation situation at a controlled facility Backup power supply High radiation resistance – at least 50,000 Sv for UDKG-37 Failure diagnostics The possibility of using the system for dosimetric monitoring of both pulsed and continuous gamma radiation The possibility of using the DKS-AT1123 dosimeter autonomously as a wearable device

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

Transmission of units of absorbed dose, directed, individual dose equivalents and their beta radiation power as part of the working standard of absorbed dose (PD) and absorbed dose power (MPD) of beta radiation in a tissue equivalent substance. ▪ Use of closed radionuclide beta radiation sources 90Sr+90Y (BIS-50, 22 GBk), 85Kr (KAC.D3, 15 GBk) and 147Pm (BIP-50, 10 GBk) ▪ Formation of a reference field from sources by a mobile emitter unit using smoothing filters ▪ Source holders with shutter and protective screens ▪ Calibrated length rods and laser device for centering and digitizing ▪ A video surveillance system of readings ▪ The possibility of using an automated extrapolation chamber as part of the installation to reproduce the absorbed dose (absorbed dose rate) of beta radiation in the tissue ▪ Measurement of ionization currents from 1 fA when using an extrapolation chamber and a precision electrometer ▪ Software for installation operation, calibration and calculations ▪ An alarm and blocking system, control of photon radiation levels in the measurement room and operator room

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”

A simple and inexpensive radiation monitoring system for radiation-hazardous facilities, such as radionuclide source storages, isotope warehouses, clinical radionuclide diagnostics and therapy departments, PET centers, metrological laboratories where work with ionizing radiation sources is carried out, etc.

▪ Rapid adaptation to changes in the radiation background ▪ Audible and light alarms when gamma radiation is detected ▪ Mobility and the possibility of forming passages ▪ Self-control of components in the process of work ▪ The possibility of continuous or episodic radiation monitoring ▪ The possibility to work from a 230V, 50Hz network or from a built-in rechargeable battery Compliance with the international standard IEC 62244:2006 Stationary radiation monitors for the detection of radioactive and special nuclear materials at state borders