[en] The steam-water mixture in a horizontal integral saturated steam generator is separated using a coarse level separator built-in above the entire heating bundle at the height of the required boiler water level. The separator consists of a system of adjacent discharge troughs forming separation channels for the steam-water mixture. The level separator increases the speed of the mixture between pipes and higher heat transfer efficiency and thus higher thermal power of the steam generator can be expected. Wherever permitted by speed conditions, the separator can also be used with vertical integral steam generators. (Z.S.)

[en] Unwanted impurities in water and steam cause serious problems in modern power plants. Substances highly soluble in hot water are particularly concerned: sodium hydroxide, sodium chloride and certain sodium phosphate salts and potassium salts. Hot water solutions of such compounds have vapor pressures lower than pure water at the same temperature and the boiling points are elevated so that concentrated liquid phases can coexist with superheated steam. The resulting phenomena and the damages caused by these impurities are reviewed: corrosion and failures of turbines, valves, heat exchangers, reheaters etc... in nuclear systems

[en] Burnout experiments are reported for uniform flux and circumferential flux tilt (maximum/average flux about 1.25) with tubes and annuli, all the experiments having uniform axial heating. These show similar results, the burnout power with flux tilt being within 10% of that with uniform flux. For the same mean exit steam quality, the local maximum flux is higher than the predicted burnout value and generally a better prediction is obtained using the average flux. (author)

[en] It is of fundamental importance in the operation of a steam generator to know the relative proportion of liquid water in the steam phase (steam quality). For that measurement purpose it is accustomed the injection of chemical tracers, in the feedwater and many techniques have been described in the literature with radioactive tracers like Na²⁴ and Cs¹³⁴. In the case of Embalse the commissioning measurement of the steam quality was performed with sodium hydroxide according to the ASME PTC 19.11-1977 Standard. However the introduction of chemicals in the steam generator water could address to unexpected corrosion phenomena and so, the current alternative explored in the present paper has been the concentration of the ions naturally present in the blowdown, the main steam and the steam reheater-condensate separator by ion exchangers. The method proved to be successful through the comparison of the results provided by different ions and in different plant conditions. (author)

No abstract available

[en] The technical level of current saturated-steam turbine constructions for nuclear power plants are outlined. +he constructional problems of high - and low - pressure houses are discussed in detail and the need for using welded steel constructions is emphasized. The problems of surface and gap erosion are discussed and the solutions of the erosion problems are summarised. A machine group with 1000 MW unit for the future Hungarian nuclear power station is described. (R.J.)

[en] Investigational results of efficiency of water separation in NPP turbine systems along the whole path of moist vapor are presented. The methods of separation on all stages of the process are considered: preturbine separation, separation in the flowing section of a turbine, separation in exhaust pipe and by-pass tubes, separation in external separators and in separators-superheaters. Efficiencies for various constructions of hollow nozzle vanes with special slots for moisture suction are compared. The procedure of moisture removal in a gap between nozzle and working grates is considered. Operation of special turbine stages-called separators in described

[en] The effect of the coolant vapor quality on the rewetting process in bottom flooding has been experimentally studied. The flow visualization showed that when the coolant vapor quality was greater than about 1%, a completely different flow pattern was noted from that observed when the coolant had no vapor quality. For a given test condition, an increasing vapor quality was accompanied by an increasing rewetting velocity. The results from the experiment are discussed in terms of the deduced heat transfer coefficient distribution and rewetting temperature. (author)

[en] The invention relates to the field of the treatment of liquids that have been subjected to radioactive contamination in the course of the exploitation of nuclear energy production installations and of radiochemical laboratories, and in particular has as its object a process for purification by continuous distillation of such liquids and an apparatus for employment of the said process. The invention can be used mainly in the nuclear field for the purification of radioactively contaminated liquids, with simultaneous production of high quality steam. 2 figs

No abstract available