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Moeck, E.O.; Wong, P.Y.
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1978
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1978
AbstractAbstract
[en] It has been proposed that the Gentilly-1 (G-1) Generating Station be modified to supply process steam to the La Prade Heavy Water Plant (LHWP), but that the generating capability of the station be retained, varying from house load (approxmately 17 MWe) to the design value (250 MWe), depending on the steam requirement of the heavy-water plant. To achieve this versatility, four reboilers would be connected to the existing steam-mains system, and a new pressure controller would be required. We describe herein an inertial analysis of the hydrodynamic behaviour of both the existing and proposed G-1 steam-mains networks. In general, the hydrodynamic behaviour of the proposed steam-mains network would be about the same as that of the existing network, during disturbances of low frequency (< 1 Hz), at nominal operating conditions
Primary Subject
Source
May 1978; 71 p
Record Type
Report
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AbstractAbstract
[en] In order to increase the safety of a PWR plant, it is suggested to install a further safety valve in the steam line coming from the steam generator. The pressure threshold of this second safety valve is lower than that of the first. In case of accident, the second safety valve can be shut off. (HP)
[de]
Um die Sicherheit einer DWR-Anlage zu erhoehen, wird vorgeschlagen, an der vom Dampferzeuger ausgehenden Dampfleitung ein weiteres Ueberdruckventil anzubringen. Der Ansprechdruck dieses zweiten Ueberdruckventils ist kleiner als der des ersten. Im Stoerfall ist das zweite Ueberdruckventil absperrbar. (HP)Original Title
Kernreaktoranlage
Primary Subject
Source
29 Sep 1977; 6 p; DE PATENT DOCUMENT 2345580/B/; Also available from Dt. Patentamt, Muenchen (FRG); 4 figs.
Record Type
Patent
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AbstractAbstract
[en] The live steam pipework system of the twin loop PWR has two pairs of live steam pipes with tee-offs, safety valves and outer shut-off valves. The steam raising units are situated inside the containment. Transverse connections are provided so that for unintentional closing of the shut-off valves the steam of a steam raising unit can be passed to the turbine via the second live steam pipe and is not blown off to the atmosphere. (DG)
[de]
Das Frischdampf-Leitungssystem des Zwei-Kreis-DWR besitzt zwei Paare von Frischdampfleitungen mit T-Abzweigungen, Sicherheitsventilen und aeusseren Abschlussorganen. Die Dampferzeuger befinden sich innerhalb des Containments. Querverbindungen sind vorgesehen, so dass bei einem unmotivierten Schliessen eines der Abschlussorgane der Dampf eines Dampferzeugers ueber die zweite Frischdampfleitung an die Turbine weitergeleitet und nicht in die Atmosphaere abgeblasen wird. (DG)Original Title
Frischdampf-Leitungssystem fuer einen Druckwasser-Reaktor
Primary Subject
Source
10 Jul 1986; 11 Feb 1975; 5 p; DE PATENT DOCUMENT 2505633/C/; ?: 11 Feb 1975
Record Type
Patent
Country of publication
Reference NumberReference Number
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INIS IssueINIS Issue
Karpenko, A.N.
Anchor/Darling Valve Co., Bala Cynwyd, Pa. (USA)1977
Anchor/Darling Valve Co., Bala Cynwyd, Pa. (USA)1977
AbstractAbstract
[en] The valve for PWRs and BWRs, with diameters up to 1.25 m, for temperatures from -1800C to about 6000C and pressures up to over 50 bar, is designed for high reliability and long useful life. Two circular valve discs are moved as isolating elements in their plane across the steam direction and brought before the valve seat within a valve chamber. Shortly before reaching this final position, each disc is rotated by a small amount about its axis. Only after reaching the final position a double-wedge, further pushed forward between both discs, produces the necessary contact pressure. By revolving and frictionless closing caking together at high stresses and temperature variation is prevented and permanent tightness assured. The valve body is moved in a cylinder, cast on the valve housing, by means of a stepped piston. Its larger diameter is guided in a second cylinder flanged on above. In the cover of the second cylinder a pilot valve is mounted being controlled over 2 parallel solenoid valves by means of compressed air. In normal operation process steam from the valve chamber serves to move the stepped piston with the valve chamber. On closing of a bore, connecting both cylinder spaces, by the pilot valve the main valve is opened. If the pilot valve is opened the steam through the connecting bore is acting on both piston stages and closing the main valve. On loss of steam (pipe break) or for testing purposes one or the other cylinder space over solenoid valves is acted upon by auxiliary energy or evacuated, the main valve thus being controlled. (HP)
[de]
Das Ventil fuer DWR und SWR mit Durchmessern bis 1, 25 m, fuer Temperaturen von -1800C bis ca. 6000C und Druecke bis ueber 50 bar, ist auf hohe Lebensdauer und Zuverlaessigkeit ausgelegt. Zwei Kreis-Ventilscheiben als Verschlusselemente werden in ihrer Ebene quer zur Dampfrichtung bewegt und innerhalb einer Ventilkammer bis vor die Ventilsitze gebracht. Kurz vor dieser Endstellung wird jede Scheibe geringfuegig um ihre Achse gedreht. Erst nach Erreichen der Endstellung erbringt ein zwischen beiden Scheiben weiter vorgeschobener Doppelkeil den noetigen Anpressdruck. Durch Verdrehen und reibungsfreies Schliessen wird ein Festbrennen bei hoher Belastung und Temperaturwechsel verhindert und dauernde Dichtheit gesichert. Der Ventilkoerper wird mittels eines Stufenkolbens in einem dem Ventilgehaeuse angegossenen Zylinder bewegt. Sein groesserer Durchmesser ist im darueber angeflanschten zweiten Zylinder gefuehrt. Im Deckel des zweiten Zylinders sitzt ein Pilotventil, das durch 2 parallele Magnetventile mittels Pressluft gesteuert wird. Im Normalfall dient Betriebsdampf aus der Ventilkammer zur Bewegung des Stufenkolbens mit dem Ventilkoerper. Das Verschliessen einer, beide Zylinderraeume verbindenden, Bohrung durch das Pilotventil laesst das Hauptventil oeffnen. Bei geoeffnetem Pilotventil beaufschlagt der Dampf ueber die Verbindungsbohrung beide Kolbenstufen und schliesst das Hauptventil. Bei Dampfausfall (Leitungsbruch) oder zu Pruefzwecken wird der eine oder andere Zylinderraum ueber Magnetventile mit der Hilfsenergie beaufschlagt oder entlueftet und so das Hauptventil gesteuert. (HP)Original Title
Absperrventil, insbesondere in Hauptdampfleitungen von Kraftwerksanlagen
Primary Subject
Secondary Subject
Source
13 Jan 1977; 33 p; DE PATENT DOCUMENT 2626508/A/; Available from ZAED. Also available from Dt. Patentamt, Muenchen (FRG); 12 figs.
Record Type
Patent
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Berndt, L.
Babcock - Brown Boveri Reaktor G.m.b.H., Mannheim (Germany, F.R.)1978
Babcock - Brown Boveri Reaktor G.m.b.H., Mannheim (Germany, F.R.)1978
AbstractAbstract
[en] A blocking device for use in secondary pipelines. The device ensures that, in any kind of operation and at any possible case of disturbance, at least one of the two pipelines transporting a medium which is under pressure is open. To solve this task, the two openings of the slide are formed as long holes twice as long as the slide's shutting move corresponding with the pipeline diameters which are to be blocked. (orig.)
[de]
Absperrarmatur fuer zweistraengige Rohrleitungen, die sicherstellt, dass in jedem Betriebszustand und bei jedem nur denkbaren Stoerfall mindestens eine der zwei - ein unter Druck stehendes Medium fuehrenden - Rohrleitungen geoeffnet ist. Geloest wird diese Aufgabe dadurch, dass die beiden Oeffnungen des Schiebers als Langloecher ausgebildet sind, die doppelt so lang sind wie die dem abzusperrenden Rohrleitungsdurchmesser entsprechende Schliessbewegung des Schiebers. (orig.)Original Title
Absperrarmatur fuer zweistraengige Rohrleitungen
Primary Subject
Source
2 Feb 1978; 6 p; DE PATENT DOCUMENT 2546496/B/; Also available from Dt. Patentamt, Muenchen (FRG)
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Rogers, J.M.
UKAEA Atomic Energy Establishment, Winfrith (UK). Reactor Systems Analysis Div1989
UKAEA Atomic Energy Establishment, Winfrith (UK). Reactor Systems Analysis Div1989
AbstractAbstract
[en] This report presents RELAP5/MOD2 calculations of the 100% steam line break test T-2013 performed on the Westinghouse Model Boiler-2 facility (MB-2). The input deck uses a noding structure typical of what would be used for an integral rig or full plant study using the RELAP5/MOD2 code. Sensitivity calculations were performed for the break junction discharge coefficient and the separator drain line loss coefficient. (author)
Primary Subject
Source
Mar 1989; 27 p
Record Type
Report
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Lee, Na Young; Hwang, Il Soon; Yoo, Han Ill; Song, Chang Rock; Park, Sang Duk; Yang, Jun Seog
Proceedings of the Korean Nuclear Society spring meeting Vol. 11997
Proceedings of the Korean Nuclear Society spring meeting Vol. 11997
AbstractAbstract
[en] For the Korean Next Generation Reactor(KNGR) development, LBB is considered for the Main Steam Line(MSL) piping inside its containment to achieve cost and safety improvement. To apply LBB concept to MSL, leak sensors highly sensitive to humidity is required. In this paper, a ceramic material, MgCr2O4-TiO2 has been developed as a humidity sensor for MSL applications. Experiments performed to characterize the electrical conductivity shows that the conductivity of MgCr2O4-TiO2 responds sensitively to both temperature and humidity changes. At a constant temperature below 100 .deg. C, the conductivity increases as the relative humidity increases, which makes the sensor favorable for application to the outside of MSL insulation layer. But as temperature increases beyond 100 .deg. C, the sensor composition should be adjusted for the application to KNGR is to be made at temperature above 100 .deg. C
Primary Subject
Source
KAERI, Taejon (Korea, Republic of); 622 p; May 1997; p. 199-206; 1997 spring meeting of the Korean Nuclear Society; Kwangju (Korea, Republic of); 30-31 May 1997; Available from KNS, Taejon (KR); 16 refs, 2 figs
Record Type
Miscellaneous
Literature Type
Conference
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Song, Dong Soo; Suh, Jeong Kwan; Yoon, Duk Joo; Kim, In Hwan
Proceedings of the KNS spring meeting2011
Proceedings of the KNS spring meeting2011
AbstractAbstract
[en] This study is to present the relaxation of the pressure and temperature(P/T) for Subcompartment during Main Steam Line Break (MSLB). The doubleended MSLB in the steam bunker corresponds to the limiting accident in the point of maximum P/T. The analysis results for the steam bunker with LOFTRANCOMPARE for M/E and P/T, respectfully, show that the maximum pressure difference is 1.45bar and the maximum temperature is 250 .deg. C. The temperature is too high to qualify the equipment for these environmental Temperature (generic limit 182 .deg. C) conditions. It is recommended to optimize the temperature result. To do so RELAP-TRAPSCO are used to analyze mass/energy (M/E) release and P/T. Finally, the result of RELAPTRAPSCO shows that the peak temperature is lower than that of LOFTRAN-COMPARE
Primary Subject
Source
Korean Nuclear Society, Daejeon (Korea, Republic of); [1 CD-ROM]; May 2011; [2 p.]; 2011 spring meeting of the KNS; Taebaek (Korea, Republic of); 26-27 May 2011; Available from KNS, Daejeon (KR); 3 refs, 5 figs
Record Type
Miscellaneous
Literature Type
Conference
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AbstractAbstract
[en] The erosion corrosion behaviour of stationary components subjected to wet steam and hot water in powerstation plants is a phenomenon to which more attention has been paid internationally during the last few years. Experimental model investigations on a wet steam erosion corrosion test rig were carried out on behalf of powerstation operators at the TU Dresden. Their aim was the creation of documents for the development of the summary erosion corrosion wear on samples of unalloyed steel at different wet steam parameters, omitting exact knowledge on the proportion of the components corrosion, erosion due to wall thrust stress and drop impact erosion in the complex wear process. The empirical model derived from the series of experiments carried out for calculating erosion corrosion rates depending on the parameters describes the relationships in the defined range of validity with sufficient accuracy. (orig.)
[de]
Die Erosionskorrosion nassdampf- und heisswasserbeaufschlagter ruhender Bauteile von Kraftwerksanlagen ist ein Phaenomen, dem in den letzten Jahren international starke Aufmerksamkeit gewidmet wurde. Im Auftrag von Kraftwerksbetreibern liefen auch an der TU Dresden experimentelle Modelluntersuchungen an einem Nassdampf-Erosionskorrosionspruefstand. Deren Ziel war die Schaffung von Unterlagen zur Entwicklung des summarischen Erosionskorrosionsabtrags an Proben aus unlegiertem Stahl bei unterschiedlichen Nassdampfparametern unter Verzicht auf genauere Kenntnisse ueber die Anteile der Komponenten Korrosion, wandschubspannungsbedingte Erosion und Tropfenschlagerosion am komplexen Verschleissprozess. Das aus den durchgefuehrten Versuchsreihen abgeleitete empirische Modell zur Berechnung parameterabhaengiger Erosionskorrosionsraten beschreibt die Verhaeltnisse in dem definierten Gueltigkeitsbereich mit ausreichender Genauigkeit. (orig.)Original Title
Abschaetzung des Erosionskorrosionsabtrags an Bauteilen aus unlegiertem Stahl bei Beaufschlagung mit Nassdampf
Primary Subject
Record Type
Journal Article
Journal
Wissenschaftliche Zeitschrift der Technischen Universitaet Dresden; ISSN 0043-6925;
; CODEN WZTUA; v. 40(5/6); p. 19-26

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Jaegtnes, K.O.; Braytenbah, A.S.
Westinghouse Electric Corp., Pittsburgh, PA (USA)1979
Westinghouse Electric Corp., Pittsburgh, PA (USA)1979
AbstractAbstract
[en] In accordance with the present invention, a power plant includes a steam source to generate superheat and reheat steam which flows through a turbine-generator and an associated bypass system. A high-pressure and an intermediate-pressure turbine portion drive a first electrical generating means, and a low-pressure turbine portion drives a second electrical generating means. A first flow of superheat steam flows through the high-pressure portion, while a second flow of reheat steam flows through the intermediate and low-pressure portions in succession. Provision is made for bypassing steam around the turbine portions; in particular, one bypass means permits a flow of superheat steam from the steam source to the exhaust of the high-pressure portion, and another bypass means allows reheated steam to pass from the source to the exhaust of the low-pressure portion. The first and second steam flows are governed independently. While one of such flows is varied for purposes of controlling the rotational speed of the first generating means according to a desired speed, the other flow is varied to regulate a power plant variable at its desired level. (author)
Primary Subject
Source
9 Jan 1979; 30 p; CA PATENT DOCUMENT 1045835/A/; Available from Commissioner of Patents, Ottawa-Hull, Canada K1A 0E1
Record Type
Patent
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