[en] The results are given of investigations on the electrostatic effects influence on the radioactive aerosols filtration. The investigations were performed by means of the radioisotope method. Filters were investigated bouth in the charged state and in the conditions of the electrostatic charge removal by means of the radioisotope eliminator. Filter's charge polarity as well as the filtering nozzles with different degree of compaction of the saim amount of filtering material were changed. Changes of the relative filter efficiency depending on the filtering material density as well as the dependance of penetration and capture of aerosols in the electrically excited and neutral filters of different designe have been investigated. (I.T.)

[en] Estimation of the nonradioactive methods of filters efficiency determination and tracer techniques are given. The methods are stated and discriptions of the instrumentation for estimation of the filters efficiency are given, in particular: methodology of production of the radioactive synthetic test-aerosols by means of the disperse and steamcondensation aerosol generators; the radio isotope method of the aerosol filters investigations; the methodology of filtartion efficiency determination. The results are given of the radioisotope investigations of filters; properties of the artificial radioactive test-aerosols; characteristics of filters, determined by the tracer techniques. Curves are given for the filtration efficiency of the viscose filtering nozzles of different density depending on the filters load. (I.T.)

[en] Sources of radioactive contamination of nuclear power plant compartments and reasons of radioactive isotopes appearance in coolant are concidered. It has been established that as for the nuclear power plants with WWR type reactors, main source of radioactive contamination is presented by radionuclides contained in corrosion products of structural materials. Characteristics of the basic structural materials are given for thouse used in WWR blocks and list of typical radionuclides in corrosion products is presented. Demands are stated for protective anticorrosive materials and also metodology for selection of particular decontamination method is given. Classification of decontamination problems at nuclear pover plant is given and methods of the primary coolant circuit decontamination and also decontamination of removable equipment and inner surfaces of equipment and compartments are stated. Decontamination processes by oxidation-reduction method, by steam emulsion method, by compact jets of desorptive solution, by means of easely removable polymer coatings, by the foam method of decontamination, decontamination by dry sorbents and electrochemical method of decontamination are stated. (I.T.)

[en] The application of a conical aerosol centrifuge - the conifuge is described as an aerosol spectrometer for investigation of the granulometric composition of radioactive aerosols. Application of the radioisotope method of measurement permits to determine the particles distribution according to their mass, analogous to their granulometric composition, quickly and with the great thrustworthiness. Discription of the improved conifuge and the changes in the aerosol-spectrometric method of analysis are given. The improved radioisotope methodology of analysis essentialy raised precision and thrustworthiness of the results obtained. The experimental results are given of the radioisotope analysis of granulometric composition of aerosols by means of the improved conifuge. (I.T.)

[en] Method for determination of pollution spreading in the earth atmosphere from a nuclear power plant is stated. The method is that a compound, the main element of which has high value of the neutron activation cross-section, on the given metheorological conditions is dispersed in the atmosphere. After this, in the preliminary determined points, samples of air is taken and the labeling substance contained in them is subjected to the neutron irradiation and subsequient determination of its activ y is performed. On the basis of the data obtained, migration of the substance, its local concentrations and distribution of the concentrations are determined. The method for modeling of pollution spreading; choice of the labeling substance; method of production and dispersing of the labeling substance in the atmosphere; the methods of samples taking and samples preparation and analysis are given. (I.T.)

[en] Facility for desactivation and burial of radioactive wastes has been built in the site with cley soil and has been intended for desactivation liquid radioactive wastes and biological wastes and for burial of solid wastes and solidificated liquid wastes. Data are given concerning types and amounts of wastes and ways for their collection. Collection of wastes is done in centralised mode. Wastes can be solid, ore liquid. Liquid wastes can be collected either in the non processed form or in the form of concentrates. Description of the technology applied in the facility and design of the building for radioactive wastes processing are given. The technological process includes: reception of the wastes collected; decontamination of equipment and rooms, contaminated during wastes handling; unloading, storage and purification of liquid wastes; discharge of surplus clean water; cementation of concentrates; bituminization of biological wastes. The method used for concentration of liquid wastes includes precipitation and ion exchange. For final burial of wastes four types of underground stores are used: the store for solid wastes where wastes in containers and polyethylene bags and also bituminized biological wastes are laid with cement mixture containing radioactive concentrates; store for solidificated liquid organic wastes; store for closed radiation sources of low actiVity; store for closed radiation sources of high activity. (I.T.)

[en] General features and future trends of research and development activities in the field of industrial applications of nuclear methods in Hungary are reported

[en] Calibration radiograms were made to determine the real particle size from radiographic spot diameters. The radioactive metallic particles of high dispersity were produced by spark evaporation and condensation of the electrodes containing (sup110m)Ag and ¹⁹²Ir isotopes. The aerosols were fractionated by centrifuging. The construction and operation of the aerosol generator, the centrifuge and the exposure box is described in detail. The spot diameters were measured by particle size analyzator and microdensitometer. RRB (Rosin, Rommler, Sperling) diagram was plotted as a function of diameter, for the characterization of spot size distribution. (K.A.)

[en] Differences between the identifications of large grains (up to some 10 microns) and submicron particles, the disadvantages of the microscopic method are reviewed. Model ¹⁹²Ir fine-grains were used for studying the reconstruction of the real particle sizes from the autoradiographic spot diameters. The particles of different size were exposed up to 240 hours with several films. The examinations carried out with an Opton TGZ-3 particle-size analyser on 2500 samples and the Bartha and Kozma type microdensitometer showed good results, although they needed a very complicated process. The development of the method is going on. (K.A.)

No abstract available