[en] The technical requirements, design and main technical characteristics of the pump for dosing corrosion and radioactive liquids with capacity up to 5 l/h are described. The design is based on the popular sixvertical split casing pump. The pump has four separate pump membrane type blocks with nonstraight hydraulic membrane control. The membranes are made of the cold worked CrNi(18/10)type stainless steel with thickness up to 0.1 mm and have the lifetime up to 3000 hours. The remote pump heads are used for pumping radioactive fluids when the pumping goes behind the safe wall, separating the pump from a hot lab. The tests showed that the pump secures the satisfactory accuracy of dozing and uniformity of pumping and that it is really possible to achieve the required life time of 10000 hours by this pump

[en] The problem of localization of liquid radioactive wastes conformably to the project of the Leningradian nuclear power plant is considered. Technical and economic estimation of the methods were considered conformably to the composition of the nuclear plant wastes with in a year of operation cited in the paper. Estimations has been made on two variants of technology. The first variant, - storage of liquid radioactive concentrates in tanks and the second variant, - solidification of liquid wastes by bituminization with subsequent burial of the salt-bitumen compound. Economic calculations have been done in confirmity with methodology accpted at the meeting of specialists from the CMEA member - countries in September 1968. Comparative technical and economic indices of localization of liquid radioactive wastes by the methods mentioned conformably to the project of the Leningradian nuclear power plant are given. It has been shown that in sp:te of the fact that bituminization were more complicated technological process in comparison to the storage of liquid radioactive concentrates in tanks, as to the safety of storage and technical and economic indices were cocerned the method of bituminization had considerable advantages. (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] The experience in the field of spent nuclear fuel transportation in the CMEA member-states and also in France, West Germany and the USA is reviewed. Represented are some characteristics of transportation casks, railway wagons and spent assemblies with the storage time ranging from 0.5 to 3 years

[en] The world experience in spent nuclear fuel shipments is summarized. Major attention is paid to the development of safe, reliable and economical casks, to the choice of the most efficient spent fuel transport (motorway, railway and maritime) and to some international legal and organizational aspects of the problem. Among those considered are both ''dry'' and ''wet'' designs of casks with different biological shields from gamma radiation (steel, lead, depleted uranium) and neutrons (boron, cadmium, water) and different cooling systems. Limits on cask weight and optimum time of spent fuel storage before shipment influence heavily the choice of a particular material, design and dimensions of casks

[en] It is proved that from the economical and technical points of view there is no reason to build devices for purification of small amounts of radioactive sewage in the points of their origin. Great amounts of liquid wastes with different composition in respect with type of waste and concentration of nuclides is originated at nuclear power plants and isotope laboratories. These liquid wastes is expedient to purify at the place of their origin. It is practical to collect and process liguid radioactive wastes separatelly depending on their type. Problems of purification of great amounts of sewage from the atomic power plant laundry are discussed. These sewage contain great amounts of detergents and little salts and radionuclides. Main processes of the sewage processing include precipitation, filtration, concentration of slurries by centrifugation, solidification of slurries and solid wastes burial. Normally, precipitation and coagulation are the chemical processing methods for radioactive sewage. Presence of detergents in sewage makes difficulties for the precipitation and coagulation processes. Satisfactory results of the radioactive sewage purification, when these sewage contain different detergents, can be obtained by means of combination of different chemical and physical an chemical methods. Results of laboratory investigations on different methods of purification of radioactive sewage with high concentration of detergents are given. (I.T.)

[en] The LMOM2 laboratory extractor as to its effectiveness of plutonium and uranium separation, present in the organic solution after the first extraction was tested. The separation principle is the uranium(4) reduction of plutonium(4) up to plutonium(3). Plutonium(3) is incapable of creating complexes with tributylphosphate and passes into a water phase. The LMOM2 extractor is a counterflow 16-stage extractor with the mechanical phase mixing. The nitric acid uranium, plutonium and hydrazine distributions in the extractor at the device productivity of 5.0 and 7.4 ml of solution per minute were experimentally found. The purification coefficients of plutonium from uranium and of uranium from plutonium are determined. The experiments performed on the extractor have shown that the choice of the process flow diagram of uranium and plutonium separation is correct. The extractor, operating in accordance with the given diagram, provides for the high coefficients of plutonium separation from uranium

[en] Processes of production and purification (necessary for fabricating fuel elements) of powdery uranium dioxide with particle size up to 1000 μm and more have been studied. Developed is continuous process of UO₂ production with above particle size by converting uranium hexafloride into UO₂ solid particles in fluidized bed while their interaction with water vapor and hydrogen on the uranium dioxide nucleus material. The method allows to conduct continuous selection from the apparatus of UO₂ powder fraction with particle size near 1000 μm without nucleus material additional feed

[en] The experience in research and development works on reprocessing of the thermal reactor spent fuel in the CEA countries in 1971-1975 is reviewed. The fuel element preparation for regeneration, water regeneration methods and their provision were the main themes of researches aimed at developing and improving technology and equipment for the WWER spent fuel regeneration. Considered were the papers analyzing the fuel element decladding and dissolving, the solution preparation, the synthesis and the investigation of sorbent extractant and diluent physico-chemical properties and methods of their regeneration. The investigation results of redox processes and methods of separation of transuranium elements and separate fission products from high-active solutions of reprocessing of the WWER-400 type fuel elements are presented. The results of testing and improving extraction diagram variants of the WWER spent fuel reprocessing are presented Much attention is given to the problems of extraction process kinetics. The above works are estimated with provision for the main trends of the development of spent fuel element regeneration technology in the world practice

[en] State of and prospects for the application of various types of radioactivity logging and other nuclear methods are discussed when prospecting, explorating and developing the non-ferrous metal deposits in Czechoslovakia. Measuring instruments being used in every above case are described