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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”

Appointment: Measurement of the ambient dose equivalent (MAED) power of gamma radiation during radiation reconnaissance and operational control of radioactive contamination of the area. Installations can be installed on cars and other mobile means, except for air.

The installation is intended for use in gas-aerosol emission control systems in order to determine the volumetric air flow in ventilation systems by measuring the linear air flow velocity at local points of the dimensional section, as well as for measuring air temperature and humidity at local points. The measuring system of the installation complies with GOST 12.3.018-79 (SSBT. Ventilation systems. Methods of aerodynamic tests).

Installation for verification and calibration of individual beta radiation dosimeters. Properties The unit transmits units of absorbed dose (PD) and absorbed dose rate (MPD) of beta radiation in a tissue equivalent substance at a depth corresponding to a surface density of 7 mg•cm-2; the transition to units of the individual equivalent of the Hp dose (0.07) in sieverts from units of beta radiation absorbed in the tissue in gray is carried out using conversion coefficients recommended by the international standard ISO 6980-3:2006; the installation can be used in metrological bodies for verification of individual beta radiation dosimeters such as DMC 2000 XB, EPD Mk2 and others.

Purpose: measurement of the ambient dose equivalent of N*(10) gamma radiation; measurement of ambient dose equivalent of N*(10) gamma radiation (operator dose).

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

▪ 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

Purpose: BAS: The unit is designed to provide light and sound signals under various conditions of controlled radiation conditions when connected to technical means that have a communication port with the unit (BOP, UDA-1AB, UDI-1B, UDG-1B, etc.). BAS-1c: The unit is designed to provide light and sound signals under various conditions of a controlled radiation environment, and operates under the control of an external device. The unit can be used in connection with individual technical means of radiation monitoring or as part of radiation monitoring systems and complexes, as well as with other compatible technical means that provide data exchange over communication lines organized on the basis of the RS-485 interface, using the DiBus exchange protocol (BOP-1M).

Purpose: processing of information received from detection units (primary converters); data transmission to the information network; data transfer to a portable computer (remote control tuning PN-PC); storage of threshold settings and parameters of detection units (primary converters); power supply and diagnostics of detection units (primary converters); output of threshold exceeding signals to built-in sound and LED alarms and to remote alarm units (BAS/BAS-1c); output of discrete signals (dry contacts); archiving of data in non-volatile memory.

A small-sized device for measuring the power of the ambient dose equivalent and the ambient dose equivalent of X-ray and gamma radiation. The case is made of impact-resistant ABS plastic Convenient menu Search mode

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

Purpose measurement of the ambient dose equivalent of N*(10) gamma radiation; measurement of ambient dose equivalent of H*(10) gamma radiation; assessment of surface contamination with radionuclides.