Atomtekh

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”

Small-sized devices for measuring the power of the ambient dose equivalent and the ambient dose equivalent of X-ray and gamma radiation, as well as measuring the flux density of beta particles (AT6130). Durable metal case Convenient menu Selective measurement of beta and gamma radiation in mixed fields (AT6130) Measurement of dose rate up to 100 mSv/h (AT6130D) Search mode Headphones for working in noisy environments (on request)

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

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.

▪ 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

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).

A unique highly sensitive device for monitoring dose loads on the lens, mucous membranes and skin Spectrum display mode when connected to a PC It is not intended for measuring the natural radiation background

Deliveries in the CIS are carried out by LLC NPP RADIKO 249035, Kaluga region, Obninsk, Marx Avenue, 14 Phone: 8(48439) 4-97-16, 4-97-18 / Fax: 8(48439) 4-97-68 E-mail: main@radico.ru / Web site: http://www.radico.ru Control of exceeding the threshold value of the total activity of radionuclides 51Cr, 54Mn, 58Co, 59Fe, 65Zn, 95Nb, 100mAg, 103Ru, 124Sb, 141Ce, 144Ce in the lungs; 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

Calculation of the expected effective dose of internal radiation per year from incorporated 137Cs and 134Cs 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

Irradiator with a typical collimator Rotary drum magazine sources in tungsten and lead protection Software control of the movement of sources and positioning of the mobile platform An alarm and blocking system, radiation monitoring system to ensure the safety of the installation Control from the operator panel or computer with verification automation functions

Intelligent spectrometric type detection unit AT1320V: The possibility of radiation monitoring of mushrooms and berries in a 10-liter container box in 20 seconds AT1320S: During the measurements, a preliminary analysis of the radionuclide composition of the sample is carried out. The activity is calculated based on the results of identification of radionuclides present in the controlled sample Methodological support of measurements

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