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AbstractAbstract
No abstract available
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Source
Atomic Energy of Canada Ltd., Chalk River, Ontario; p. l0-12; Sep 1971
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Report
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AbstractAbstract
No abstract available
Original Title
Vier Jahre Betriebserfahrung mit dem MZFR
Primary Subject
Record Type
Journal Article
Literature Type
Progress Report
Journal
Atomwirt., Atomtech; v. 16(4); p. 181-184
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Brynda, W.; Chow, J.G.Y.; Hoffman, K.; Tichler, P.
Brookhaven National Lab., Upton, N.Y. (USA)1970
Brookhaven National Lab., Upton, N.Y. (USA)1970
AbstractAbstract
No abstract available
Primary Subject
Source
Jan 1970; 22 p
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Report
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AbstractAbstract
[en] Safety of the various types of nuclear reactor (light water, heavy water, gas-cooled) is compared. Failures of various systems and components (e.g. cooling-medium failure) are analysed. (H.E.G.)
Original Title
Sicherheitskonzepte und Sicherheitsmassnahmen
Primary Subject
Record Type
Journal Article
Journal
Schweizerische Bauzeitung; v. 95(44); p. 794-800
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AbstractAbstract
No abstract available
Primary Subject
Source
Nov 1978; 2 p; Short communication only.
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Report
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AbstractAbstract
[en] The invention relates to nuclear reactor fuel element assemblies in which the coolant employed is light or heavy water. The assembly is one in which nuclear fuel rods are supported in a cluster and spaced apart by transverse grids so that the spaces between the rods form sub-channels through which main reactor coolant is passed. In order to provide auxilliary cooling it is proposed that auxilliary cooling conduits be located amongst the cluster of fuel rods. These conduits have coolant ejection holes in the wall arranged circumferentially in a predetermined pattern which is determined by the position of the conduit in the cluster and by the axial distance of the ejection hole along the conduit. (J.R.)
Original Title
(Secondary coolant circuit design)
Primary Subject
Source
12 Aug 1975; 14 p; AU PATENT DOCUMENT 75/83874/A/; Copies available from the Commissioner of Patents, Canberra; Open to public inspection 20 Jan 1977, priority USA 29 Aug 1974.
Record Type
Patent
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AbstractAbstract
[en] ASTEC, jointly developed by IRSN and GRS, is considered as the European reference code since it capitalizes knowledge from the European research on the domain. The CESAM project aims at its enhancement and extension for use in severe accident management (SAM) analysis of the nuclear power plants (NPP) of Generation II-III presently under operation or foreseen in near future in Europe, spent fuel pools included. Within the CESAM project 3 main types of research activities are performed: -) further validation of ASTEC models important for SAM, in particular for the phenomena being of importance in the Fukushima-Daichi accidents, such as reflooding of degraded cores, pool scrubbing, hydrogen combustion, or spent fuel pools behaviour; -) modelling improvements, especially for BWR or based on the feedback of validation tasks; and -) ASTEC applications to severe accident scenarios in European NPPs in order to assess prevention and mitigation measures. An important step will be reached with the next major ASTEC V2.1 version planned to be delivered in the first part of 2015. Its main improvements will concern the possibility to simulate in details the core degradation of BWR and PHWR and a model of reflooding of severely degraded cores. A new user-friendly Graphic User Interface will be available for plant analyses
Primary Subject
Source
Societe Francaise d'Energie Nucleaire (SFEN), 75 - Paris (France); 3390 p; 2015; p. 1562-1570; ICAPP 2015: Nuclear Innovations for a low-carbon future; Nice (France); 3-6 May 2015; Available (USB stick) from: SFEN, 103 rue Reaumur, 75002 Paris (France); 15 refs.; This record replaces 48079372
Record Type
Book
Literature Type
Conference
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Related RecordRelated Record
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AbstractAbstract
[en] Post-dryout heat transfer from fuel elements is important in the safety analysis of water-cooled nuclear reactors. Limited availability of relevant data has resulted in much uncertainty in the prediction of post-dryout fuel surface temperatures. Recent studies have permitted the development of a better prediction technique based on non-equilibrium effects. (author)
Primary Subject
Source
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs; p. 8-10; Feb 1976
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] A nuclear fuel element is described, comprising a cluster of nuclear fuel rods seperated by transverse grids so as to define interspaces for the axial flow of reactor coolant. At least one of the spaces is occupied by an axially extending auxilliary coolant, conduit with lateral holes through which an auxilliary coolant is sprayed into the cluster. The invention in particular describes a deflector means extending from the transverse grid into a position in front of the holes for deflecting the auxilliary coolant spray on to parts of the fuel rods inaccessible to auxilliary coolant. (J.R.)
Original Title
(Secondary coolant circuit design)
Primary Subject
Source
21 Aug 1975; 9 p; AU PATENT DOCUMENT 75/84166/A/; Copies available from the Commissioner of Patents, Canberra; Open to public inspection 20 Jan 1977, priority USA 29 Aug 1974.
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The nuclear fuel assembly described includes a cluster of fuel elements supported at a distance from each other so that their axes are parallel in order to establish secondary channels between them reserved for the coolant. Several ducts for an auxiliary cooling fluid are arranged in the cluster. The wall of each duct is pierced with coolant ejection holes which are placed circumferentially to a pre-determined pattern established according to the position of the duct in the cluster and by the axial distance of the ejection hole along the duct. This assembly is intended for reactors cooled by light or heavy water
[fr]
On presente un assemblage combustible nucleaire comportant une grappe d'elements combustibles supportes a distance les uns des autres de maniere que leurs axes soient paralleles pour delimiter entre eux des canaux secondaires reserves au fluide de refroidissement. Plusieurs conduits pour un fluide de refroidissement auxiliaire sont disposes dans la grappe, chaque conduit presentant dans sa paroi des trous d'ejection du fluide de refroidissement menages circonferentiellement selon une configuration predeterminee qui est etablie par la position du conduit dans la grappe et par la distance axiale du trou d'ejection le long du conduit. Cet assemblage est destine aux reacteurs refroidis par eau legere ou lourdeOriginal Title
Assemblage combustible nucleaire; auxiliary cooling for light or heavy water reactor fuel clusters
Primary Subject
Secondary Subject
Source
19 Aug 1975; 13 p; FR PATENT DOCUMENT 2282697/A/; Available from Institut National de la Propriete Industrielle, Paris (France); priority claim: 20 Aug 1974, UK.
Record Type
Patent
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