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Anderson, P.M.
General Atomic Co., San Diego, CA (USA)1977
General Atomic Co., San Diego, CA (USA)1977
AbstractAbstract
[en] This invention covers a process for supplying fuel to a nuclear reactor core inside a reactor vessel. The core includes a certain number of zones each one of which has a certain number of significantly horizontal layers, each layer comprising a number of individual fuel elements, the fuel elements of the respective layers forming appreciably vertical columns. The fuel elements, at least in the lowest layer, being spent, the process enables the zones to be supplied in sequence. In each zone, unspent fuel elements are withdrawn from the vessel in at least one of the columns but not in all, in order to uncover one or more spent fuel elements which are then removed from the vessel. The unspent fuel elements are moved inside the vessel to other locations (including the previous locations of at least some of the fuel elements previously withdrawn, whether or not spent) in order to uncover one or more other spent fuel elements which are also withdrawn from the vessel. The unspent fuel elements that were withdrawn from the vessel are then moved to other parts of the core and fresh fuel elements are placed in the vessel, at least in the upper layer of fuel elements. This series of operations is repeated in the other zones so as to complete the refuelling of the core
[fr]
Selon l'invention, un procede est prevu pour le ravitaillement en combustible d'un coeur de reacteur nucleaire a l'interieur d'une cuve de reacteur. Le coeur comporte un certain nombre de zones dont chacune comprend un certain nombre de couches sensiblement horizontales, chaque couche comprenant un certain nombre d'elements individuels de combustible, les elements de combustible de couches respectives constituant des colonnes sensiblement verticales. Les elements de combustible, au moins dans la couche inferieure, etant epuises, le procede permet le ravitaillement en sequence des zones. On retire de la cuve pour chaque zone, des elements combustible non-epuises dans au moins une des colonnes mais non dans toutes, pour decouvrir un ou plusieurs elements de combustible epuises et on retire de la cuve les elements de combustible epuises mis a decouvert; on deplace a l'interieur de la cuve, les elements de combustible non-epuises vers d'autres emplacements (y compris les emplacements precedents de certains, au moins, des elements de combustible prealablement retires, epuises et non-epuises), pour mettre a decouvert un ou plusieurs autres elements de combustible epuises, et on retire de la cuve ces autres elements de combustible epuises. On place les elements de combustible non-epuises qui ont ete precedemment retires de la cuve dans d'autres emplacements dans le coeur, et on place dans la cuve de nouveaux elements de combustible non-epuises, au moins dans la couche superieure des elements de combustible. On repete cette suite d'operations pour les autres zones afin d'achever le ravitaillement du coeurOriginal Title
Procede pour ravitailler en combustible un coeur de reacteur nucleaire
Primary Subject
Source
5 Sep 1977; 17 p; FR PATENT DOCUMENT 2363867/A/; Available from Institut National de la Propriete Industrielle, Paris (France); Priority claim: 7 Sep 1976, US.
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Record Type
Journal Article
Journal
Nuclear Canada/Canada Nucleaire; v. 14(2); p. 9
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Reference NumberReference Number
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INIS IssueINIS Issue
AbstractAbstract
[en] After the first fuel cycle of the Sizewell B plant, which encompassed 270 days of uninterrupted power generation, refueling was completed in 54 days and 17 hours, which is the third best result achieved at a four-loop power plant supplied by Westinghouse. The whole refueling sequence and circumstances are described in detail
Original Title
Prvni vymena paliva v Jaderne elektrarne Sizewell B predcila ocekavani
Primary Subject
Source
Based on article published in Nuclear Engineering International (1996), v. 508, p. 34-36.
Record Type
Journal Article
Literature Type
Translation
Journal
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Reference NumberReference Number
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INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Hinweis auf die oeffentliche Bekanntmachung gemaess Para. 15 Abs. 3 und Para. 17 der Atomrechtlichen Verfahrensverordnung ueber eine Nachtragsgenehmigung fuer das AVR-Atomversuchskraftwerk in Juelich der Arbeitsgemeinschaft Versuchsreaktor GmbH wegen des 'Einsatzes von Brennelementen der 21. AVR-Nachfuellcharge in das AVR-Atomversuchskraftwerk'. (13. Nachtrag zum Bescheid Nr. 7/8 AVR vom 21. Dezember 1983). Vom 13. Februar 1984
Primary Subject
Secondary Subject
Source
Published in summary form only.; CODEN: BDZRA.
Record Type
Journal Article
Journal
Bundesanzeiger; ISSN 0344-7634; 
; v. 36(36); p. 1588
; v. 36(36); p. 1588
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Reference NumberReference Number
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INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
Conference on reactor operating experience; Albuquerque, NM; 3 Aug 1975; Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society. Supplement; v. 21(Suppl. 1); p. 19-20
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Chandra, U.; Marathe, A.D.; Swarup, A.; Chandra, A.K.; Kumar, V.
Symposium on nuclear reactor instrumentation [held at] Bombay [during] December 20-23, 1976 [papers]1976
Symposium on nuclear reactor instrumentation [held at] Bombay [during] December 20-23, 1976 [papers]1976
AbstractAbstract
[en] A computer based control system developed for operating fuelling machines in nuclear power stations is described. The system requirements control strategy, diagnostic features etc are explained. (A.K.)
Primary Subject
Source
Department of Atomic Energy, Bombay (India); p. 33-38; 1976; p. 33-38; Department of Atomic Energy; Bombay; Symposium on nuclear reactor instrumentation; Bombay, India; 20 - 23 Dec 1976
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Mysels, K.J.
General Atomic Co., San Diego, Calif. (USA)1976
General Atomic Co., San Diego, Calif. (USA)1976
AbstractAbstract
[en] A method of refueling the fuel columns in the active core of a nuclear reactor and including fuel columns comprised of substantially equal stacks of fuel elements is described. The method comprises the steps of: a) completely removing a predetermined number of adjoining fuel columns to initially create a plurality of adjoining vacant columns; b) filling the vacant columns with at least one fresh hexagonal shaped fuel element, and a plurality of complementary hexagonal shaped fuel elements transferred from a single fuel column adjoining at least one of the vacant columns by laterally transferring plurality of complementary fuel elements; c) discarding a number of fuel elements from single adjoining fuel column equal to the number of fresh fuel elements placed in one of vacant columns to thus create a new vacant column; d) repeating steps b and c until all of fuel columns in active core have been refueled except a number of finally remaining vacant columns equal to the number of initially created vacant columns; and refilling remaining vacant columns with a number of hexagonal shaped fuel elements as necessary to establish full fuel columns
[fr]
On decrit une methode de rechargement de colonnes de combustible dans le coeur d'un reacteur nucleaire comprenant des colonnes de combustible formees par des empilages d'elements combustibles en nombre sensiblement egal. La methode comprend les operations suivantes: a) des colonnes adjacentes de combustible sont enlevees en nombre predetermine de facon a former des emplacements libres; b) un des emplacements libres est garni par au moins un element combustible neuf et des elements combustibles en nombre complementaire, provenant d'une colonne adjacente a un des emplacements libres, ces elements complementaires etant amenes a l'emplacement voulu par un deplacement sensiblement lateral; c) des elements combustibles de la colonne adjacente en nombre egal a celui des elements combustibles neufs introduits dans l'emplacement sont enleves laissant un nouvel emplacement libre pour une colonne; d) on repete les operations b et c jusqu'a ce que toutes les colonnes de combustible dans le coeur aient ete regarnies a l'exception d'un nombre d'emplacements de colonnes finalement laisses libres, egal au nombre de colonnes initialement enlevees; on remplit les colonnes restees vacantes avec le nombre d'elements combustibles necessaire pour retablir les colonnes entieres de comOriginal Title
Conduite d'un reacteur nucleaire a elements combustibles empiles en colonnes, par transfert d'elements en colonnes; HTGR type reactors
Primary Subject
Source
1 Apr 1976; 22 p; FR PATENT DOCUMENT 2313744/A/; Available from Institut National de la Propriete Industrielle, Paris (France); Priority claim: 3 Apr 1975, US.
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Sechster Brennelementwechsel beim 345-MW-Kernkraftwerk Obrigheim abgeschlossen
Primary Subject
Source
Short communication only.
Record Type
Journal Article
Journal
Atom und Strom; v. 21(7); p. 74
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Barabach, Boris; Deltour, Philippe.
CEA, 75 - Paris (France)1976
CEA, 75 - Paris (France)1976
AbstractAbstract
[en] This invention concerns a system for enabling a nuclear reactor core to be loaded whilst avoiding the errors in positioning them and, in particular, their introduction into the core in conditions likely to bring about nuclear excursions. It applies particularly to the case of an experimental reactor of the pool type. The system in question includes an upper deflecting grille with side openings, fitted above the core and parallel to the lower grille support, for introducing control members on a level with their position. A central aperture enables the fuel elements to be passed in one by one. The passage through this central aperture is prevented by pivoting bolts retracting under the effect of the actuating gear carried by the control members, so that the loading of any fuel element by axial entry into the central aperture then by transverse displacement in order to place it between two adjacent control members, cannot take place until all the control members have been introduced beforehand in the core
[fr]
La presente invention est relative a un dispositif permettant de proceder au chargement du coeur d'un reacteur nucleaire par des elements combustibles, en evitant les erreurs de positionnement de ces elements et notamment leur introduction dans le coeur dans des conditions susceptibles d'entrainer des risques d'excursions nucleaires. Elle s'applique plus particulierement dans le cas d'un reacteur experimental du type piscine. Le dispositif considere comporte, monte au-dessus du coeur et parallelement a la grille de support inferieure, une grille superieure de detrompage, comprenant des ouvertures laterales pour l'introduction, au droit de leurs emplacements dans le coeur, des elements de controle. Une ouverture centrale permet l'engagement un a un des elements combustibles. Le passage a travers cette ouverture centrale est empeche par des verrous pivotants s'effacant sous l'effet de moyens d'actionnement portes par les elements de controle de telle sorte que le chargement d'un element combustible quelconque par engagement axial dans l'ouverture centrale puis par deplacement transversal pour mise en place entre deux elements de controle adjacents, ne puisse s'effectuer qu'une fois tous les elements de controle prealablement introduits dans le coeurOriginal Title
Dispositif pour eliminer les erreurs de chargement dans un reacteur nucleaire; pool type reactors
Primary Subject
Source
28 Oct 1976; 15 p; FR PATENT DOCUMENT 2369657/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
No abstract available
Primary Subject
Source
Conference on reactor operating experience; Albuquerque, NM; 3 Aug 1975; Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society. Supplement; v. 21(Suppl. 1); p. 21-22
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
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