REFERENCE SIGNAL GENERATOR OF DOPPLER MODULATOR DRIVER OF MÖSSBAUER SPECTROMETER

This research work is devoted to the development of reference signal generator of Mössbauer spectrometer. This generator forms signal of special form thus providing necessary lowering of motion of Doppler modulator with low error value. As reference signal generator, a programmable function generator on the base of an AT90S8515 microcontroller and a 12-bit digital-to-analog converter were used

A portable radiometric system for nuclear medicine

It's shown suggested methods for diagnosing pathological processes in biological objects using a developed portable radiometric system with four gamma-ray detectors. Designed portable radiometric system was used to make 2D imaging of anatomical structures. The system can value pharmacokinetics in several points of wide area of interest at the patient body. In this study specially designed phantoms were used. Phantom models of the liver and blood circulation system were made to assay radiometric system. The construction concept and possible applications of the system in the practice of radionuclide diagnostic studies in vivo are presented. © 2018 Elsevier Lt

COMPARISON OF CONCENTRATION METHODS FOR SAMPLES OF GASEOUS EMISSIONS FROM AN INDUSTRIAL REACTOR FACILITY FOR DETERMINING THE RADIONUCLIDE COMPOSITION

The results of measuring emissions of inert radioactive gases from an industrial nuclear reactor on a semiconductor gamma spectrometer, using cryogenic concentration sampling and the sampling method with concentration under pressure are shown. Comparison of methods is carried out

Dynamics Investigation of Emissions Noble Radioactive Gases during Normal Operation of Industrial Nuclear Reactor

The results of noble gases emissions monitoring of industrial nuclear reactor emissions during the campaign, after a shutdown for scheduled preventive maintenance and after a physical start-up with a subsequent increase in power are shows

COMPARATIVE EVALUATION OF DOSES TO PERSONNEL OF RADIOLOGICAL DIVISIONS

A comparative analysis of radiation doses of personnel of radionuclide diagnostics departments was carried out

RADIATION IMPACT OF RESEARCH NUCLEAR REACTORS IN NORMAL OPERATION

Research reactors as well as energy reactors release into environment radiological, chem-ical, thermal and other stressors. Environmental impact also includes water intake because this factor can be important for biota. All these factors should be studied qualitatively and quantitatively.Авторы выражают благодарность Международному агентству по атомной энергии за содействие в сборе установочных данных

SCINTILLATION DETECTOR FOR FAST AND THERMAL NEUTRONS

FIELD: dosimetry of fast and thermal neutrons and gamma radiation.SUBSTANCE: proposed scintillation detector is intended for using in the radiation monitoring systems for fissile material detection (uranium, plutonium, californium and articles from them). The scintillation detector consists of transducer and unit for electron processing of signals. The transducer consists of two scintillators, fulfilled in the form of plates with plane-parallel and touched faces, being in the optical contact. The scintillators are located in the single case. The first (plastic) scintillator is fabricated in the form of a wedge from organic hydrogen-containing material, selectively sensitive to fast neutrons, which causes the light scintillations owing to recoil protons. This scintillators is intended for fast neutron detection. The second (glass) scintillator is fabricated from the 6Li silicate glass and is intended for thermal neutron detection. Both scintillators are equipped with light-resetting film and forms a single sensory scintiunit. The scintiunit is equipped with a lead collimator and is located together with the last in a polyethylene box-storage. The transducer has also a photoelectric multiplier, installed at the end face of the plastic scintillator. The photoelectric multiplier signals are applied at the unit of electron signal processing. This unit ensures counting of the number of pulses, induced by scintillations in both scintillators.EFFECT: increased efficiency of detection of both fast neutrons, and thermal ones.1 cl, 1 dwg.Изобретение относится к области дозиметрии быстрых и тепловых нейтронов и гамма-излучения. Оно пригодно для использования в комплексах и системах радиационного контроля, предназначенных для обнаружения делящихся материалов (урана, плутония, калифорния и изделий из них). Технический результат изобретения: обеспечение регистрации как быстрых, так и тепловых нейтронов с повышенной эффективностью. Сущность: детектор состоит из датчика и блока электронной обработки сигналов. Датчик содержит два размещенных в едином корпусе сцинтиллятора, выполненных в виде пластин с плоскопараллельными соприкасающимися гранями, находящимися в оптическом контакте. Первый - пластиковый - сцинтиллятор изготовлен в виде клина из органического водородсодержащего вещества, избирательно чувствительного к быстрым нейтронам, которые за счет протонов отдачи вызывают в нем световые вспышки, и служит для регистрации быстрых нейтронов. Второй сцинтиллятор - стеклянный (на основе 6Li-силикатного стекла) - предназначен для регистрации тепловых нейтронов. Оба сцинтиллятора снабжены световозвращающей пленкой и образуют единый сенсорный сцинтиблок, оборудованный свинцовым коллиматором и размещенный вместе с последним в полиэтиленовом пенале-накопителе. Датчик содержит также фотоэлектронный умножитель, устанавливаемый с торца пластикового сцинтиллятора, сигналы с которого поступают на блок электронной обработки сигналов, обеспечивающий подсчет числа импульсов, вызванных сцинтилляциями, возникающими в обоих сцинтилляторах. 1 ил