[en] A process for the preparation of technetium-99m labeled pharmaceuticals is disclosed. The process comprises initially isolating technetium-99m pertechnetate by adsorption upon an adsorbent packing in a chromatographic column. The technetium-99m is then eluted from the packing with a biological compound to form a radiopharmaceutical

[en] A chromatographic column for generating technetium-99m isotopes and technetium-99m labeled pharmaceuticals in a simple two-step process is described. Technetium-99m pertechnetate in a first step is isolated by adsorption upon an adsorbent packing. Then the technetium-99m in a second step is eluted from the packing, either with an immediately labeled biological compound to form a radiopharmaceutical, or by a controlled volume of eluant to produce a 99m-technetium-bearing eluate of a desired specific concentration. (Official Gazette)

No abstract available

[en] The stages of the implementation of the diagnostic system at the first unit of the Dukovany nuclear power plant are described. The project was designed of the system of in-service diagnostics with the aim of monitoring selected components of the primary circuit using a vibroacoustic diagnostic system. Piezoelectric acceleration pick-ups were used - 34 pieces placed on the reactor, the primary circuit piping, the main closing valves and the circulating pump, the steam generator and the pressurizer. The spatial density of neutron flux was measured as a complement of the vibroacoustic measurements. A program was compiled for testing the coordination of the individual assemblies of the system of in-service diagnostics, of functional pathways, the condition of components of the primary circuit and its parameters. The subsystems are described used for monitoring vibrations of the components of the primary circuit and for the detection of loose parts, as well as the possibilities of the ADT 4410 computer system used. (J.C.)

[en] The demands are summed up on the software for the diagnostic system of the Dukovany nuclear power plant in the period of the integrated hydraulic trial, the physical and power start-up of the unit. These demands have followed from experience gained with the first and second units of the plant which showed that it was very difficult to locate, using the installed diagnostic system, the source of the failure by analyzing an arbitrary signal from the sensor output. The functions are defined which the diagnostic system software must fulfil during the start-up when it is necessary to detect defects of delivered components including defects of assembly such as to allow their removal during the revision of the installation. Special attention is devoted to the identification of loose parts in the primary circuit and to the possibility of calibrating and simulating the system of loose parts in operation. The software of the system must proceed from an estimate of weight and kinetic energy of the loose part which must be identified, including the distance between the point of impact and the sensor, and the time of contact of the part with the point of impact. (Z.M.)

[en] The principles are given used in selecting the testing points and constructing the testing chain of the diagnostic system for the primary and secondary coolant circuits of a WWER 440 type nuclear power plant. The block for signal reception and analysis is described and a block diagram is shown of the entire diagnostic system. The specifications are given of the pressure fluctuation amplifier and of the vibration amplifier and pickup. Data are processed electronically using a CAMAC system. (J.B.)

No abstract available

[en] Some results are presented of measuring vibroacoustic noise and temperature changes in the steam generator, the economizer, the main circulating pump, the main closing valve, and the primary coolant circuit of unit 1 of the Dukovany nuclear power plant. The measuring and evaluation instruments used are described. The measured values show that the major source of vibrations in the primary circuit are the main circulating pumps from which the vibrations spread at the basic speed frequency and its 5th and 15th harmonics. For the steam generator which did not produce steam during the test, significant vibrations were recorded in the range of natural frequencies of the heat exchange tubes, i.e., between 90 and 220 Hz. It was found that the measurement of time changes in local temperatures could practically be used in estimating the residual life of loaded nodes of the primary circuit. The vibroacoustic and thermocouple diagnostic testing chains developed and manufactured in Czechoslovakia were found fail-safe in the operating conditions of the power plant. (A.K.)

No abstract available

[en] Values of impurity concentrations in boiler water as well as some adverse characteristics of blowdown and sludge blow-off systems of WWER-440 steam generators are given as obtained by a series of experimental and theoretical studies. A short overview of degradation effects of steam generator materials and characteristics of blowdown and sludge blow-off systems outside the steam generator are presented. The effects of impurity concentrations in boiler water and blowdown and sludge blow-off waters on intercircuit leak evaluation during the steam generator operation are briefly discussed. (author) 3 tabs., 5 figs., 7 refs