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AbstractAbstract
[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.)
Original Title
Horizontalni telesovy parogenerator
Primary Subject
Source
15 Aug 1987; 28 Nov 1983; 5 p; CS PATENT DOCUMENT 240561/B1/; CS PATENT APPLICATION PV 8828-83; Application date: 28 Nov 1983
Record Type
Patent
Country of publication
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Lindsay, W.T. Jr.
Proceedings of the 8. International conference on the properties of water and steam. Giens, September 23-27, 19741975
Proceedings of the 8. International conference on the properties of water and steam. Giens, September 23-27, 19741975
AbstractAbstract
[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
Primary Subject
Secondary Subject
Source
v. 2 p. 713-720; 1975; Editions Europeennes Thermiques et Industries; Paris, France; 8. International conference on the properties of water and steam; Giens, France; 23 Sep 1974
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[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)
Primary Subject
Source
Mar 1966; 34 p; Also available from H.M. Stationery Office; Country of input: International Atomic Energy Agency (IAEA); 6 refs, 13 figs, 3 tabs
Record Type
Report
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INIS VolumeINIS Volume
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AbstractAbstract
[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)
Original Title
Determinacion del titulo de vapor en los generadores de la central nuclear Embalse
Primary Subject
Source
1999; 3 p; AATN; Buenos Aires (Argentina); AATN '99: 26. Annual meeting of the Argentine Association of Nuclear Technology (AANT); AATN '99: 26. Reunion anual de la Asociacion Argentina de Tecnologia Nuclear (AATN); San Carlos de Bariloche (Argentina); 9-12 Nov 1999; 1 tab.
Record Type
Miscellaneous
Literature Type
Conference
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AbstractAbstract
No abstract available
Primary Subject
Source
Deutsches Atomforum e.V., Bonn (F.R. Germany); p. 277-280; 1970; ZAED; Leopoldshafen, F.R. Germany
Record Type
Book
Literature Type
Conference; Progress Report
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[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.)
Original Title
Telitett goez-turbinak atomeroemuevekhez
Primary Subject
Source
2 refs.
Record Type
Journal Article
Journal
Mueszaki Koezlemenyek - a Lang Gepgyar Mueszaki es Gazdasagi Tajekoztatoja; ISSN 0230-1679;
; p. 7-24

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Reference NumberReference Number
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AbstractAbstract
[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
Original Title
Problemy separatsii vlagi v turboustanovkakh AEhS
Primary Subject
Source
For English translation see the journal Thermal Engineering (UK).
Record Type
Journal Article
Journal
Teploehnergetika; ISSN 0040-3636;
; (no.2); p. 41-46

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AbstractAbstract
[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)
Primary Subject
Record Type
Journal Article
Journal
International Journal of Heat and Mass Transfer; ISSN 0017-9310;
; v. 28(1); p. 139-146

Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Golubev, E.K.; Lensky, A.R.; Glazov, E.E.; Bersenev, V.A.; Vakulenko, B.F.; Mikhailov, V.S.; Shiryaev, A.A.
Rockwell International Corp., Golden, CO (United States). Rocky Flats Plant. Funding organisation: USDOE, Washington, DC (United States)1989
Rockwell International Corp., Golden, CO (United States). Rocky Flats Plant. Funding organisation: USDOE, Washington, DC (United States)1989
AbstractAbstract
[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
Primary Subject
Source
Nov 1989; 16 p; CONTRACT AC34-90DP62349; Available also from OSTI as DE91018412; NTIS; INIS; US Govt. Printing Office Dep
Record Type
Report
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Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Tillequin, J.
Nuclex 72. International Nuclear Industries Fair, 16-21 October 1972, Basel/Switzerland1972
Nuclex 72. International Nuclear Industries Fair, 16-21 October 1972, Basel/Switzerland1972
AbstractAbstract
No abstract available
Original Title
Amelioration du concept des secheurs-resurchauffeurs pour centrales nucleaires
Primary Subject
Source
Anon; Paper 5, 10 p; 1972; Nuclex 72; Basel, Switzerland; 16 Oct 1972; 10 figs.
Record Type
Report
Literature Type
Conference
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Country of publication
Reference NumberReference Number
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