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Tidmarsh, J.J.
British Nuclear Design and Construction Ltd., Whetstone1975
British Nuclear Design and Construction Ltd., Whetstone1975
AbstractAbstract
No abstract available
Primary Subject
Source
19 Feb 1975; 5 p; GB PATENT DOCUMENT 1384701/B/
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Anthony, A.J.; Groves, M.D.
Combustion Engineering, Inc., New York (USA)1980
Combustion Engineering, Inc., New York (USA)1980
AbstractAbstract
[en] This invention refers to a fuel unit comprising a simple system for locking it in position near its lower end on to a nuclear reactor core support, in such a manner that the locking action can be selectively operated from the upper end of the unit. Under this invention, this device enables locking and unlocking to be effected without using any part of the supporting structure to an excessive extent. The lock can be released from a distance in the event of any failure of a locking component
[fr]
Cette invention concerne un bloc a combustible comportant un dispositif simple destine a verrouiller ce bloc vers le bas sur un support de coeur de reacteur nucleaire, de maniere que le verrouillage puisse etre commande selectivement a partir de l'extremite superieure du bloc. Le dispositif selon l'invention permet d'effectuer le blocage et le deblocage sans user excessivement une partie quelconque de la structure de support. Le dispositif de verrouillage peut etre debloque a distance dans le cas d'une defaillance d'un element de blocageOriginal Title
Bloc a combustible de reacteur nucleaire et dispositif pour retenir vers le bas un tel bloc a combustible
Primary Subject
Source
13 Jun 1980; 22 p; FR PATENT DOCUMENT 2441903/A/; Available from Institut National de la Propriete Industrielle, Paris (France); Priority claim: 13 Nov 1978, US.
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Kennedy, J.M.; Wang, C.Y.; Belytschko, T.B.
Structural mechanics in reactor technology. Transactions. Vol. E1979
Structural mechanics in reactor technology. Transactions. Vol. E1979
AbstractAbstract
[en] The upper internal structures which are located above the core and below the head cover may play a significant role in the hydrodynamic of an energy excursion such as a hypothetical core discruptive accident (HCDA) by mitigating the slug impact on the head. For purposes of studying these effects, a structural model was developed for the upper internals and the support columns which connect them to the head of the reactor vessel. This structural model can be used either by itself or in an interactive mode with one of the hydrodynamics codes developed at Argonne, such as ICECO or REXCO. (orig.)
Primary Subject
Source
Jaeger, T.A.; Boley, B.A. (eds.); Commission of the European Communities, Brussels (Belgium); Bundesanstalt fuer Materialpruefung, Berlin (Germany, F.R.); International Association for Structural Mechanics in Reactor Technology; p. E2/2 (1-8); ISBN 0444 85361 8;
; 1979; p. E2/2 (1-8); North-Holland Publishing Co; Amsterdam, Netherlands; 5. international conference on structural mechanics in reactor technology (SMIRT-5). 9. international seminar and 2. international seminar on structural reliability of mechanical components and subassemblies of nuclear power plants and 2. international seminar on containment of fast breeder reactors (CONFABRE-2); Berlin, Germany, F.R; 9 - 21 Aug 1979; INKA-CONF--79-321-153

Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Formanek, F.J.; Schukei, G.E.
Combustion Engineering, Inc., Windsor, CT (USA)1980
Combustion Engineering, Inc., Windsor, CT (USA)1980
AbstractAbstract
[en] A nuclear fuel assembly is described, adapted to be locked into first mating surfaces on a core support stand, comprising a lower end fitting having posts for resting on the stand; elongated hook members pivotally connected at one end to the lower end fitting and having a second mating surface at the other end to engage the first mating surfaces; actuating means located between the posts on the lower end fitting and being vertically movable relative to the end fitting; and rigid links pivotally attached at one end to the hook members intermediate the connection of the hook members to the end fitting and the second mating surface and pivotally attached at the other end to the actuating means, the link having a length between the pivoted connections such that the second mating surface on the hook members locks into engagement with the first mating surfaces on the stand as the links approach the horizontal. (author)
Primary Subject
Secondary Subject
Source
23 Jul 1980; 7 p; GB PATENT DOCUMENT 2038402/A/
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
IEEE nuclear science symposium; New York, N. Y; 4 Nov 1970
Record Type
Journal Article
Journal
IEEE (Inst. Elec. Electron. Eng.), Trans. Nucl. Sci; v. NS-18(1); p. 388-394
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Formanek, F.J.; Schukei, G.E.
Combustion Engineering, Inc., New York (USA)1980
Combustion Engineering, Inc., New York (USA)1980
AbstractAbstract
[en] The object of this invention is to harness the force of the ascending coolant of the reactor to actuate a locking mechanism holding the fuel unit in position against the core support. The invention makes for easy unlocking of the unit so as to facilitate its removal. The fuel unit is held in position near its lower end by a compact device, of easy fabrication and use, that does not cause any significant drop in the pressure of the coolant in the reactor vessel. Under the invention, the fuel unit can be unlocked from a distance in the event of any failure of the normal locking components
[fr]
L'invention a pour objet d'utiliser la force du courant ascendant du fluide de refroidissement du reacteur pour actionner un mecanisme de verrouillage maintenant le bloc a combustible en place contre le support du coeur. L'invention permet un deverrouillage aise du bloc afin de faciliter son demontage. Le bloc a combustible est retenu vers le bas au moyen d'un dispositif peu volumineux, d'une fabrication et d'une mise en oeuvre aisees et ne provoquant pas une chute sensible de la pression du fluide de refroidissement dans la cuve du reacteur. Le bloc a combustible selon l'invention peut etre deverrouille a distance dans le cas d'une defaillance des organes normaux de verrouillageOriginal Title
Bloc a combustible nucleaire
Primary Subject
Source
20 Jun 1980; 15 p; FR PATENT DOCUMENT 2442491/A/; Available from Institut National de la Propriete Industrielle, Paris (France); Priority claim: 24 Nov 1978, 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
Literature Type
Progress Report
Journal
J. Nucl. Energy; v.25(1); p.35-40
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] A nuclear reactor core stabilizing arrangement is described wherein a plurality of actuators, disposed in a pattern laterally surrounding a group of elongated fuel assemblies, press against respective contiguous fuel assemblies on the periphery of the group to reduce the clearance between adjacent fuel assemblies thereby forming a more compacted, vibration resistant core structure. 7 claims, 4 drawing figures
Original Title
Patent
Primary Subject
Source
26 Oct 1976; 6 p; US PATENT DOCUMENT 3,987,860/A/
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
Meeting of the American Nuclear Society; Washington, District of Columbia, USA; 27 Oct 1974; See CONF-741017-- Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Trans. Amer. Nucl. Soc; v. 19 p. 154
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] A model testing has been performed to investigate the flow characteristics of a vortex chamber, which plays a role of a flow switch and passively controls the discharge flow rate. This method of passive flow control is a matter of concern in the design of advanced nuclear reactor systems as an alternative to the active flow control to provide emergency water to the reactor core in case of postulated accidents like LOCA (Loss-of-Coolant accident). By changing the flow direction in the vortex chamber and varying the flow resistance inside the chamber, the vortex chamber can control passively the injection flowrate. fundamental characteristics such as discharge flow rate and pressure drop of the vortex chamber are measured, and its parametric effects on the performance of the vortex chamber are also systematically investigated. (author)
Primary Subject
Source
14 refs., 1 tab.,10 figs.
Record Type
Journal Article
Journal
Transactions of the Korean Society of Mechanical Engineers. B; ISSN 1226-4881;
; v. 24(3); p. 338-345

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