[en] A summary is presented of the major scientific, technical and economic results achieved by the Institute of Nuclear Research in Rez near Prague in the year 1985. Research and development was mainly oriented to nuclear power: problems of nuclear safety of PWR reactors were studied; experiments were made and evaluated in the field of reactor physics of PWR's, in cooperation with CMEA countries also of fast reactors; the properties were tested of reactor materials under various conditions; in-pile diagnostic techniques were developed for WWER and BN reactors. Research in the field of fuel cycle chemistry was mainly oriented to the treatment of radioactive waste waters and solutions, to the solidification of radioactive wastes, and to the fluoride technology of reprocessing spent fuel from fast reactors. Attention was also devoted to the compilation of technical standards. Also tackled were research problems related to the use of ionizing radiation, such as radiation processing, the research and development of radiopharmaceuticals, neutron activation analysis and neutron radiography. Attention was also devoted to radiation safety. The experimental equipment of the Institute also served the production of radiopharmaceuticals, the development and manufacture of semiconductor detectors, the analysis of samples for the Central Testing Laboratory, and experimental irradiation. The Institute also provided computer and information services. The social programme was oriented to personnel development, housing and catering, health care, the work environment and the recreation of employees. The Institute has achieved good economic results. (J.B.)

[en] Major scientific, technical and partly also economic results are reported achieved in 1986 by the Institute of Nuclear Research. The research and development efforts were mainly focused on applied research in nuclear power, namely, nuclear safety of the reactor core and fuel elements, neutron processes in the LR-0 reactor, radiation resistance of reactor materials, experimental and computer-aided research in reactor technology, fuel cycle chemistry (coolant and radioactive waste treatment, radioactive waste solidification, fuel reprocessing). In the sphere of ionizing radiation, work was concentrated on radiation resistance of plastics, radiation sterilization, radiation food treatment, radiopharmaceuticals production, applications of neutron activation analysis, neutron radiography, and radiation safety. The science management work consisted in coordination of the solution of science and technology development projects, and in international cooperation. The sphere of production and services covered the production of radiopharmaceuticals, semiconductor detectors of ionizing radiation, services provided by the Central Inspection Laboratory, irradiations services, data processing and information services. The social program of the Institute was aimed at improving the qualifications of the personnel, care of their housing, catering, working environment and recreation. (J.B.)

[en] An international conference on new trends in nuclear power production with regard to the fuel cycle was held in Brussels from April 26 to 30, 1982. The content of the problem area was discussed in 16 technical sessions and 5 plenary sessions which took up the following problems: the role of the nuclear power, experience with the operation of nuclear power plants, spent fuel processina, industrial and non-power applications of nuclear energy, trends and prospects of all aspects of nuclear energy uses. The basic ideas on the development of nuclear power may be summed up as follows: light water reactors should be completed with and later replaced by fast reactors, the closure of the fuel cycle in the shortest possible time is economically indispensable and technically, ecologically and proliferation-wise possible. After the year 2000, it will be necessary to extend the use of nuclear sources for the generation of industrial heat, or for the production of secondary fuels. Fusion reactors cannot be put to industrial use sooner than in 50 years time. (M.D.)

[en] The most important scientific, technical and partly also economic results attained in 1987 by UJV Rez are summed up. Research and development work in nuclear power is oriented to nuclear safety, reactor physics, reactor materials, reactor technology, chemistry of the fuel cycle and standardization. In the field of the use of ionizing radiation the problems resolved included radiation technologies, radiopharmaceuticals, neutron activation analysis and neutron radiography. Some of the works were also oriented to radiation safety. In the field of production and services the study was oriented to the production of radiopharmaceuticals, semiconductor ionizing radiation detectors, services of the Central Control Laboratory, irradiation services, computer and information services. The social program of the Institute was oriented to upgrading personnel, the housing programme, catering, working environment and recreation. The organization structure of the Institute is given. (J.B.). 36 figs., 11 tabs., 101 refs., 10 colour illustrations in Supplement

[en] A review is presented of available literature data on the physical, physico-chemical and radiation properties of the UO₂-PuO₂ system, important in respect of the use of the system as thermal reactor fuel. The techniques are described of mixed fuel preparation as are the methods of quality control, radiological aspects of the (U,Pu)O₂ application, the possibility of multiple plutonium recycling, and the existing experience with reactor applications. (author). 24 figs., 22 tabs., 84 refs

[en] One of the methods of improving the use of nuclear fuel by better control of power and reactivity coefficient distribution, thus reducing the cost of the fuel cycle, is the application of burnable neutron poison, such as Gd₂O₃. A critical review is presented of available literature data on physical and chemical properties of Gd₂O₃ and the UO₂-Gd₂O₃ system. Attention is paid mainly to the phase diagram of the system, to oxygen stoichiometry and thermodynamical properties of mixed U and Gd oxides and to thermal conductivity of the UO₂-Gd₂O₃ system. The technology is described of production of mixed uranium-gadolinium fuel pellets as well as the problems involved. A table shows the parameters of homogeneity achieved for pellets containing up to 4 wt.% of Gd₂O₃. Measures are listed necessary for testing such fuel. The neutron-physics properties of Gd and radiation behaviour of U-Gd fuel are characterized. The main benefits of Gd as a poison include relatively low poisoning of fuel by the end of the reactor campaign; it also allows suitable profiling of the radial and axial power distributions in the fuel assembly. A constraint for more extensive use of U-Gd fuel in PWR's has so far been the scarcity of data on the behavior of fuel with higher Gd concentration. (A.K.). 15 figs., 13 tabs., 68 refs

[en] The current state is described of the introduction in the world, of the technologies of light water reactor fuel cycle with emphasis on the technology of nuclear fuel production, spent fuel management, and radioactive waste processing and disposal. The basic technical and economic parameters are systematically classified of the individual stages of the fuel cycle and the overall developmental trends are outlined of providing fuel cycle services. (B.S.)

[en] Results are reported of nuclear power research including reactor physics, reactor materials, reactor technology, fuel cycle chemistry; of research in ionizing radiation applications including radiation technologies, radiopharmaceuticals, neutron activation analysis, neutron radiography. Services are outlined provided by the UJV, such as the production of radiopharmaceuticals, development and manufacture of semiconductor radiation detectors, irradiation services, data processing services, library and information centre services. (E.J.). 38 figs., 7 tabs., 107 refs

[en] A critical review is given of data on the physical, chemical end other relevant properties of fuel materials and fuel elements for HTGR reactors. Available technologies for coated particles and fuel elements fabrication and appropriate quality control are described. In-core fuel behavior and spent fuel reprocessing are briefly discussed. Basic information about uranium and thorium fuel cycles is included. (author). 17 figs., 21 tabs., 87 refs

[en] The problems are described of the research and development base of the nuclear power complex. Management of research and development should secure the complex solution of the whole problem and the time schedule of research and development work should comply with the needs of everyday practice. (E.S.)