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Meuschke, R.E.; Martinez, J.M.
Westinghouse Electric Corp., Pittsburgh, PA (USA)1977
Westinghouse Electric Corp., Pittsburgh, PA (USA)1977
AbstractAbstract
[en] The invention concerns a thermocouple receptacle and a device to be located inside a reactor, that provides a positive seating for the thermocouples immediately next to the outlet of the fuel assemblies and allows a visual inspection to be made of the position of the thermocouples
[fr]
L'invention a pour objet un receptacle de thermocouple et un dispositif destine a etre place a l'interieur d'un reacteur qui assure une assise positive des thermocouples a proximite immediate des sorties des assemblages combustibles et qui permet une inspection visuelle de la position des thermocouplesOriginal Title
Receptacle pour thermocouple a jonction chaude d'un reacteur nucleaire
Primary Subject
Source
12 Jan 1977; 9 p; FR PATENT DOCUMENT 2338551/A/; Available from Institut National de la Propriete Industrielle, Paris (France); Priority claim: 15 Jan 1976, US.
Record Type
Patent
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INIS IssueINIS Issue
AbstractAbstract
[en] A thermocouple with several electrodes is presented, its distinguishing features being a very low bulk, a small number of electrodes and a single envelope. Compared with known types of thermocouple it offers a smaller quantity of metal when used in the core of nuclear reactors. In addition the thermocouple has a small diameter and great length, up to 50m or more, and can therefore fit into narrow channels of any shape and be connected to secondary instruments without the need for compensation wires
[fr]
On presente un thermocouple a plusieurs electrodes qui se distingue par un tres faible encombrement, un petit nombre d'electrodes, une seule enveloppe. Par rapport aux thermocouples du type connu, il offre une quantite de metal moins importante lors de l'utilisation dans le coeur des reacteurs nucleaires. De plus, le thermocouple a un faible diametre et une grande longueur pouvant aller jusqu'a 50m et plus, ce qui permet sa mise en place dans les canaux etroits de tout profil et le raccordement aux appareils secondaires sans faire appel a des fils de compensationOriginal Title
Thermocouple profile a plusieurs electrodes
Source
10 Sep 1975; 9 p; FR PATENT DOCUMENT 2284991/A/; Available from Institut National de la Propriete Industrielle, Paris (France); priority claim: 10 Sep 1974, USSR.
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Secondary Subject
Source
Transactions of the American Nuclear Society 1976 international meeting; Washington, DC, USA; 14 Nov 1976; Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society; v. 24 p. 392-393
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Alekseev, V.I.; Emelyanov, I.Y.; Ivanov, V.M.; Konstantinov, L.V.; Lysikov, B.V.; Postnikov, V.V.; Rybakov, J.V.
Deutsches Patentamt, Muenchen (Germany, F.R.)1977
Deutsches Patentamt, Muenchen (Germany, F.R.)1977
AbstractAbstract
[en] The ionisation chamber is used for the measurement of powerful neutron and γ radiation at temperatures up to 8000C in the fission zone of a nuclear reactor. It consists mainly of a cylindrical housing filled with argon, a rod electrode lying on the axis of the cylinder, coaxially arranged protective electrode, and distance and insulating pieces between the elektrodes and the housing. A collector electrode made of individual, separate pieces of tube lies outside the protective electrode. The electrical connection is via a three-core coaxial cable, whose central conductor is connected to the rod electrode, whose inner sheath is connected to the protective electrode and whose outer sheath is connected to the casing. For an external diameter of less than 6 mm the lenght of the miniature ionisation chamber can be designed in 10 mm steps to 5 - 7 metres. For measuring the neutron flux, the surface of the piece of tube is covered with uranium enriched with the isotope U 235. Thus the sensitivity of the ionisation chamber is reduced with regard to thermal neutrons. (DG) 891 HP
[de]
Die Ionisationskammer dient zur Messung starker Neutronen- und γ-Strahlung bei Temperaturen bis 8000C in der Spaltzone eines KKW. Sie besteht im wesentlichen aus einem mit Ar gefuellten zylindrischen Gehaeuse, einer in der Zylinderachse liegenden Stabelektrode, einer koaxial hierzu angeordneten Schutzelektrode sowie Distanz- und Isolierstuecken zwischen den Elektroden und dem Gehaeuse. Eine Sonnenelektrode aus einzelnen, getrennten Rohrstuecken liegt ausserhalb der Schutzelektrode. Der elektrische Anschluss erfolgt ueber ein Dreileiter-Koaxialkabel, dessen Mittelleiter mit der Stabelektrode, dessen innerer Mantel mit der Schutzelektrode und dessen aeusserer Mantel mit dem Gehaeuse verbunden ist. Bei einem Aussendurchmesser kleiner als 6 mm kann die Laenge der Miniatur-Ionisationskammer auf 10 mm bis 5-7 m ausgelegt werden. Zur Messung des Neutronenflusses wird die Oberflaeche der Rohrstuecke mit dem Isotop U-235 angereicherten Uran ueberwogen. Hierdurch wird die Empfindlichkeit der Ionisationskammer gegenueber thermischen Neutronen verringert. (DG)Original Title
Ionisationskammer
Secondary Subject
Source
15 Dec 1977; 6 p; DE PATENT DOCUMENT 2437171/B/
Record Type
Patent
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Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Farcy, Paul.
CEA, 75 - Paris (France)1980
CEA, 75 - Paris (France)1980
AbstractAbstract
[en] This invention refers to a detector of particles that enables accurate determinations to be effected at high temperature, irrespective of the particle flux to which it is subjected (for example, a neutron flux in the core of a reactor) and preferentially is of elongated shape and particularly reduced radial section. According to the invention, the specifications of this detector include a body in a single piece, made of a ceramic material, in which are embedded and sealed two concentric tubular electrodes forming between them an annular chamber filled with a gas under pressure and electric wires connecting the electrodes to the outside of the body
[fr]
L'invention a pour objet un detecteur de particules permettant de realiser des mesures precises a haute temperature, quel que soit le flux de particules auquel il est soumis (par exemple, flux de neutrons dans le coeur d'un reacteur) et presentant de preference une forme allongee et de section radiale particulierement reduite. Ce detecteur selon l'invention est caracterise en ce qu'il comprend un corps en une seule piece, en materiau ceramique, dans lequel sont noyees de facon etanche deux electrodes tubulaires concentriques definissant entre elles une chambre annulaire remplie de gaz sous pression, et des fils de liaison electriques reliant les electrodes a l'exterieur du corpsOriginal Title
Detecteur de particules et son procede de fabrication
Source
24 Oct 1980; 15 p; FR PATENT DOCUMENT 2452783/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
Todt, W.H. Sr.
Westinghouse Electric Corp., Pittsburgh, PA (USA); Deutsches Patentamt, Muenchen (Germany, F.R.)1978
Westinghouse Electric Corp., Pittsburgh, PA (USA); Deutsches Patentamt, Muenchen (Germany, F.R.)1978
AbstractAbstract
[en] The neutron detector consists of a fission chamber and a compensated ionisation chamber for neutron flux between 1 and 1010/cm2/sec. The maximum flux for neutron detectors in impulse counting operation is limited by the saturation and the minimum which is detectable due to DCα signal noise. The detector contains a small quantity of UO2 which is deposited on an electrode. Part of the detector is in the form of a compensation chamber. It contains Ra226. The α signal noise is suppressed by the reduction of the U 234 content in UO2 to less than 100 ppm. The γ compensation signal can be produced by an external circuit. (DG) 891 HP
[de]
Der Neutronendetektor besteht aus einer Spaltkammer und einer kompensierten Ionisationskammer fuer einen Neutronenfluss zwischen 1 und 1010/cm2/sec. Der maximale Fluss fuer Neutronendetektoren im Impulszaehlbetrieb wird begrenzt durch die Saettigung und der minimale nachweisbare durch das Gleichstrom-α-Signalrauschen. Der Detektor enthaelt eine kleine Menge von UO2, das auf einer Elektrode aufgebracht ist. Ein Teil des Detektors ist als γ-Kompensationskammer ausgebildet. In ihr ist Ra226 enthalten. Das α-Signalrauschen wird durch die Verringerung des U-234 Gehaltes im UO2 auf kleiner 100 ppm unterdrueckt. γ-Kompensationssignal kann auch durch eine aeussere Schaltung erzeugt werden. (DG)Original Title
Neutronennachweissystem
Primary Subject
Secondary Subject
Source
19 Jan 1978; 10 p; DE PATENT DOCUMENT 2729210/A/
Record Type
Patent
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AbstractAbstract
[en] The Core Operating Limit Supervisory System (COLSS) digital monitoring system relies on signals from fixed in-core detectors to determine the peak linear heat rate of the fuel and the departure from nucleate boiling ratio thermal margin. Experience with this type of detector indicates that some failures will occur during operation. This paper describes the cause-and-effect relationship between detector failures and those COLSS parameters determined by the detector signals, the statistical methods used to determine the additional penalties incurred by detector failures, and the proposed limiting conditions for operation for the in-core detector system. 11 refs
Primary Subject
Record Type
Journal Article
Journal
Nuclear Technology; ISSN 0029-5450;
; v. 54(2); p. 145-154

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AbstractAbstract
No abstract available
Primary Subject
Source
American Nuclear Society 1975 winter meeting; San Francisco, CA, USA; 16 Nov 1975; Published in Summary Form Only.
Record Type
Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society; v. 22 p. 558-559
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Reference NumberReference Number
INIS VolumeINIS Volume
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AbstractAbstract
[en] A study has been made of the effects of various arrangements of the transducers and control rods for a height problem. The BASIRA program has been used with a BESM-6 in detailed analysis of the stability of a system with a complicated distribution of the parameters; however, the situation can be analyzed qualitatively without resort to a computer. Here a homogeneous cylindricl reactor of unit radius with zero boundary conditions. 10 refs
Primary Subject
Source
Cover-to-cover translation of Atomnaya Ehnergiya (USSR).
Record Type
Journal Article
Journal
Soviet Atomic Energy; ISSN 0038-531X;
; v. 48(5); p. 297-301

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Suvanto, A.; Welen, S.
ASEA-ATOM AB, Vaesteraas (Sweden)1976
ASEA-ATOM AB, Vaesteraas (Sweden)1976
AbstractAbstract
[en] A sensing probe device constituted by a tubular feeler member adapted to be inserted into a reactor-core and by a through-tube coxial with said feeler member, characterized in that feeler member can be telescopically introduced into said through-tube. (author)
Original Title
Hopskjutbar detektorsond; In core instruments
Primary Subject
Source
16 Feb 1976; 5 p; SE PATENT DOCUMENT 382881/B/
Record Type
Patent
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