[en] A brief description is given of the research and production of radiopharmaceuticals at the Nuclear Research Institute. Since 1974, iodine 131-labelled orthoiodohippurate and rose bengal have been produced at the WWR-S reactor. The production has also been studied of medical preparations at the cyclotron, such as fluorine 18, selenium 72, gallium 67 and the radionuclide generators germanium 68/gallium 68 and yttrium 87/strontium 87m. Procedures have been worked out of the preparation of a number of selenium 75-labelled compounds (radioprotectives and barbiturates) and bromine 82-labelled cytostatics. (Z.M.)

[en] Processes are described accompanying nucleogenesis as are the properties of atoms produced, their excitation and ionization, their reactions in the gaseous, liquid and solid phases. Processes are analyzed in binuclear reactions, especially the (n,γ) reaction, processes in radioactive transformations, in γ radiation emission, isomeric transition, and internal conversion. (M.D.)

[en] The measurement of activity of ⁹⁰Sr during its fast isolation by extraction with cobalt dicarbollide and Slovafol 909 in a nitrobenzene-carbon tetrachloride mixed solvent and re-extraction with 0.15 M Chelaton IV at pH 10.2 was investigated. The use of a liquid scintillator allows the effect of the ⁹⁰Y beta activity to be eliminated more efficiently than if the evaporation residue is measured with a solid scintillator. Traces of dicarbollide, nitrobenzene and CCl₄ passed into the aqueous solution exert an unfavorable effect by shifting the spectral curve of the ⁹⁰Sr+⁹⁰Y beta radiation towards lower energies, the shift being dependent on the concentration of the above interferents in the aqueous phase. This effect can be eliminated by extracting the aqueous phase with the same volume of octyl alcohol or amyl acetate; while removing the organic interferents, this extraction brings about no apparent loss of strontium. (author). 3 tabs., 7 figs., 5 refs

[en] The report deals with Stage 1: 'Setting out the decommissioned parts releasing procedure, especially a methodology of assessment of the parts to be released and dosimetric measurements for release', and Stage 2: 'Analysis of actually achieved contamination of critical points, especially by supplying and evaluating data obtained from operated NPPs, including existing Nuclear Research Institute reports'. The items addressed included contamination of emergency control assemblies and measurements of this contamination. (P.A.)

[en] A comprehensive overview is presented of the methods and instrumentation used for the inspection and analysis of packagings with low level radioactive wastes by a testing laboratory for quality control of various types of radioactive wastes intended for storage at surface and underground repositories/disposal sites in the Czech Republic, i.e. solid and solidified liquid reactor wastes emerging from the operation of nuclear power plants and institutional radioactive wastes from other waste generators. (author)

[en] Various glasses used for the vitrification of radioactive wastes were tested with emphasis on the leaching of elements (Si, Al, B, Mn, Li, Ca, Mg, Zn) from model vitrified mixtures. The quality of the glasses was unaffected by the presence of ²³⁹Pu. It is shown that the mixed packing of columns (integral fusing vessels) - V8 glass frit and granulated synthetic mordenite - can also be employed for fixing suspensions of iron(III) hydroxide or hydrated titanium oxide collectors with trapped plutonium. Separated from the liquid radioactive wastes, the suspension will be pumped into vessels containing fresh packing, the column will be transported into the vitrification module, and fixing will be achieved by heating at 1050 degC. Hence, the procedure for the processing of accident liquid radioactive wastes proposed previously can be extended by the use of the same vessels and the same packing also for fixing alpha contaminants. It is reasonable to assume that americium can be fixed in the same manner. A report entitled ''Sorption of plutonium and americium from weakly acid and neutral borate solutions on sorbents in a PAN matrix'' is appended. (P.A.). 15 tabs., 3 figs., 10 refs

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No abstract available

[en] The report is structured as follows: Overview of current status of characterization of hazardous wastes contaminated with radionuclides (HWCTR) in the Czech Republic (Legislative aspects; Categorization of HWCwR; Overview of HWCwR emerging from workplaces handling ionizing radiation sources; Mixed waste management in the Czech Republic); General procedure to characterized wastes of the HWCwR type (Information needed from the waste producer; Waste analysis plan - description of waste treatment facilities, verification of wastes, selection of waste parameters followed, selection of sampling method, selection of test methods, selection of frequency of analyses; Radiation protection plan; Non-destructive methods of verification of waste - radiography/tomography, dosimetric inspection, measuring instrumentation, methods usable for the determination of volume and surface activities of materials; Non-destructive invasive methods - internal pressure measurement and gas analysis, endoscopic examination, visual inspection; Destructive methods - sampling, current equipment at Nuclear Research Institute Rez; Identification of hazardous components in waste - chemical screening of mixed wastes; Assessment of immobilization waste matrices; Assessment of packaging; Safety analyses; QA and QC). (P.A.)

[en] Basic data are presented on the current state of production of commercially supplied radiopharmaceuticals including ¹³¹I-o-iodohippuran, ¹³¹I-rose begal, sup(99m)Tc-pertechnetate which have been gradually introduced in UJV in the last several years. The problems of research and development of other radiopharmaceuticals which are to be introduced in the future are reviewed. Current trends are shown of the development of nuclear medicine and an estimate is made of the future demand for radiopharmaceuticals. (author)