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Muhamad Daud; Jamaliah Shariff.
Unit Tenaga Nuklear, Bangi, Selangor (Malaysia)1984
Unit Tenaga Nuklear, Bangi, Selangor (Malaysia)1984
AbstractAbstract
[en] By using hot plate/magnetic stirrer and immersion technique, the steel corroded uniformly and their corrosion rates vary due to type of steel, time of immersion, temperature and rotation of water. Therefore the rate of general corrosion, or sealing, of steel alloys is influenced by a number of factors, those best established being the composition of the metal, time, temperature, velocity, cleanliness or roughness of the metal surface and direct contact with solutions of the other materials. (author)
Primary Subject
Source
1984; 34 p; Available from Nuclear Energy Unit, Bangi, 43000 Kajang, Malaysia
Record Type
Report
Report Number
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Robin, Marcel.
CEA, 75 - Paris (France)1975
CEA, 75 - Paris (France)1975
AbstractAbstract
[en] The invention concerns an improvement to the design of the secondary systems of a nuclear reactor with a view to making them more compact in order to make a significant saving on the lengths of piping required and on the buildings protecting them, thereby reducing the corresponding capital expenditure. As the steam generator is designed with a central return duct for the cold sodium, the sodium is driven through the system by a pump whose suction is directly coupled to the central duct of the generator. The steam generator and circulating pump unit is mounted in a sealed bay integrated in the reactor building, the connection with the intermediate exchanger in the secondary system being made by pipes passing through a leak-proof opening in the wall of the building
[fr]
L'invention concerne un perfectionnement apporte a la conception des circuits secondaires d'un reacteur nucleaire, visant a les rendre plus compacts afin de realiser une economie importante sur les longueurs de tuyauterie necessaires et sur les batiments les abritant, en reduisant de ce fait les investissements correspondants. Le generateur de vapeur etant agence pour comporter un canal central de retour du sodium froid, la circulation de ce sodium dans le circuit est assuree par une pompe dont l'aspiration est directement couplee au canal central du generateur. L'ensemble constitue par le generateur de vapeur et la pompe de circulation est monte dans un alveole etanche integre au batiment contenant le reacteur, la liaison avec l'echangeur intermediaire dans le circuit scondaire etant realisee par des conduits traversant de facon etanche la paroi du batimentOriginal Title
Perfectionnement apporte aux circuits secondaires d'un reacteur nucleaire
Primary Subject
Source
22 Aug 1975; 7 p; FR PATENT DOCUMENT 2321750/A/; Available from Institut National de la Propriete Industrielle, Paris (France)
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Schabert, H.P.; Laurer, E.
Kraftwerk Union A.G., Muelheim an der Ruhr (Germany, F.R.)1976
Kraftwerk Union A.G., Muelheim an der Ruhr (Germany, F.R.)1976
AbstractAbstract
[en] The invention concerns a quick-acting valve on the main-steam pipe of a nuclear power plant. The engineering design of the valve is to be improved. To the main valve disc, a piston-operated auxiliary valve disc is to be assigned closing a section of the area of the main valve disc. This way it is avoided that the drive of the main valve disc has to carry out different movements. 15 sub-claims. (UWI)
[de]
Die Erfindung betrifft ein Schnellschlussventil an der Frischdampfleitung einer Kernreaktoranlage. Die konstruktive Gestaltung des Ventils soll verbessert werden; dem Hauptventilteller soll ein kolbenbetaetigter Hilfsventilteller zugeordnet werden, der wiederum einen Ausschnitt der Flaeche des Hauptventiltellers verschliesst. Dadurch wird vermieden, dass der Antrieb des Hauptventiltellers unterschiedliche Bewegungen ausfuehren muss. 15 Unteransprueche. (UWI)Original Title
Kernreaktoranlage
Primary Subject
Source
4 Nov 1976; 13 p; DE PATENT DOCUMENT 2519376/A/; Also available from Dt. Patentamt, Muenchen (FRG); 2 figs.
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Schabert, H.P.; Laurer, E.
Kraftwerk Union A.G., Muelheim an der Ruhr (Germany, F.R.)1976
Kraftwerk Union A.G., Muelheim an der Ruhr (Germany, F.R.)1976
AbstractAbstract
[en] The invention concerns a quick-acting valve on a main-steam pipe of a nuclear power plant, especially one of the two pistons serving as opening mechanism. The engineering design is to be carried out in such a manner that a play between the pistons avoids mutual jamming, the safety requirements for such facilities thus being fully met. (UWI)
[de]
Die Erfindung betrifft ein Schnellschlussventil an einer Frischdampfleitung einer Kernreaktoranlage, insbesondere einen der beiden Kolben, die als Oeffnungsmechanismus dienen. Die konstruktive Gestaltung ist so zu fuehren, dass durch ein Spiel zwischen den Kolben ein gegenseitiges Klemmen vermieden wird, sodass die Sicherheitsanforderungen an solchen Anlagen voll erfuellt werden. (UWI)Original Title
Kernreaktoranlage
Primary Subject
Source
4 Nov 1976; 11 p; DE PATENT DOCUMENT 2518526/A/; Also available from Dt. Patentamt, Muenchen (FRG); 3 figs.
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The aim of this project is to perform a permanent non-pollution monitoring of the secondary cooling water for the IRT-5000 Reactor, so that any leakage from the primary cooling water to the secondary cooling water that may happen due to defect in the heat exchanger can be detected at the secondary circuit. The system consists of GM detector, analog unit which supplies the GM detector with high voltage and treat the pulses from the GM detector, microprocessor cabinet used for data processing and providing external control via relays
Primary Subject
Source
Iraq Atomic Energy Commission, Baghdad (Iraq). Nuclear Research Centre; Annual Report; [200 p.]; 1990; p. 101; Iraqi Atomic Energy Commission; Baghdad (Iraq); Available from Information Center-Iraqi Atomic Energy Commission, Tuwaitha-Baghdad, P.O. BOX 765, IRAQ
Record Type
Miscellaneous
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
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Brachet, Alain.
Electricite de France, 75 - Paris1981
Electricite de France, 75 - Paris1981
AbstractAbstract
[en] This invention concerns improvements to secondary coolant-systems for sodium cooled nuclear reactors. It further concerns a protective device for a free level mechanical pump which prevents any gas bubbles due to leaks of the working gas of the pump from entering the secondary system of the nuclear reactor
[fr]
Cette invention a pour objet des perfectionnements aux circuits caloporteurs secondaires pour reacteurs nucleaires refroidis par du sodium liquide. Elle concerne egalement un dispositif de protection d'une pompe mecanique a niveau libre qui permet d'eviter d'eventuelles remontees de bulles de gaz dues aux fuites de gaz fonctionelles de la pompe dans le circuit secondaire du reacteur nucleaireOriginal Title
Perfectionnements aux circuits caloporteurs secondaires pour un reacteur nucleaire du type refroidi par un metal liquide
Primary Subject
Source
31 Jul 1981; 8 p; FR PATENT DOCUMENT 2474744/A/; Available from Institut National de la Propriete Industrielle, Paris (France)
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Fast acting closure means are requested in PWR type reactors as well as in BWR to safely shut-off the live steam at the turbine input in the event of accident. The design and control system of steam shut-off valves acted by the fluid system and intended for PWR type reactors, are described. The role of these valves in a PWR is discussed with the specified requirements involved
[fr]
Des organes de fermeture a action rapide sont necessaires, aussi bien dans les PWR que dans les BWR, pour intercepter avec une surete rigoureuse, en cas d'incident, l'arrivee de vapeur vive a la turbine. On decrit la construction et le mode de commande de soupapes d'isolement de vapeur, actionnees par le fluide du systeme, pour reacteur a eau pressurisee. On precise le role de ces soupapes dans un PWR et les exigences qui en decoulentOriginal Title
Les soupapes d'isolement de vapeur pour reacteurs a eau pressurisee
Primary Subject
Record Type
Journal Article
Journal
Techniques de l'Energie; (no.17); p. 29-30
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Naretto, C.J.
Idaho National Engineering Lab., Idaho Falls (USA)1978
Idaho National Engineering Lab., Idaho Falls (USA)1978
AbstractAbstract
[en] A methodology, employing the concept of risk, is described which was created to aid in building an efficient spare parts inventory for the LOFT secondary coolant system
Primary Subject
Source
12 Jul 1978; 52 p; RE-A--78-072; Available from NTIS., PC A04/MF A01
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Report
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AbstractAbstract
No abstract available
Primary Subject
Secondary Subject
Source
31 Dec 1973; 2 p; Published in summary form only.
Record Type
Report
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Reference NumberReference Number
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Schrock, S.L.; Mangus, J.D.
Westinghouse Electric Corp., Pittsburgh, PA (USA)1977
Westinghouse Electric Corp., Pittsburgh, PA (USA)1977
AbstractAbstract
[en] The invention concerns a process and apparatus for detecting the position of a leak in a tube of a tubular heat exchanger of the liquid metal-water type, habitually employed in a sodium cooled nuclear reactor. Under the invention an inert gas is let in on the outside of the tubes, a pressure difference is created along the tube under test, the lower pressure taking place inside the tubes. The tube is then heated to bring about the dissociation and isolation of the reaction products which are then analysed to indicate the faulty tubes
[fr]
L'invention concerne un procede et un appareil pour detecter la position d'une fuite dans un tube d'un echangeur thermique du type metal liquide-eau, a tubes, utilise habituellement dans un reacteur nucleaire refroidi par sodium. Selon l'invention, un gaz inerte est admis a l'exterieur des tubes, une difference de pression est realisee a travers le tube essaye, la pression la plus basse s'exercant a l'interieur des tubes. Le tube est chauffe pour creer la dissociation et l'isolement des produits de la reaction, lesquels sont analyses pour indiquer quels tubes sont defectueuxOriginal Title
Methode et appareil pour localiser un tube defectueux dans un echangeur thermique de type tubulaire metal liquide-eau
Primary Subject
Source
12 Apr 1977; 16 p; FR PATENT DOCUMENT 2348483/A/; Available from Institut National de la Propriete Industrielle, Paris (France); Priority claim: 12 Apr 1976, US.
Record Type
Patent
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