Filters
Results 1 - 10 of 5608
Results 1 - 10 of 5608.
Search took: 0.034 seconds
Sort by: date | relevance |
Hista, J.C.
Societe Franco-Americaine de Constructions Atomiques (FRAMATOME), 92 - Courbevoie (France)1982
Societe Franco-Americaine de Constructions Atomiques (FRAMATOME), 92 - Courbevoie (France)1982
AbstractAbstract
[en] The structure is composed of a containment vessel having a cylindrical skirt and a dome, and a ring building surrounding the containment vessel. The ring building is composed of a cylindrical skirt and a roof, the containment vessel and the ring building rising on a joint general raft. Internal structures are positioned inside the containment vessel. The roof of the ring building is in the shape of a truncated cone or toric and is set in the cylindrical skirt of the containment vessel. The internal structures are independent of the containment vessel
[fr]
Structure de batiment reacteur comportant une toiture de batiment couronne encastree dans la jupe cylindrique de l'enceinte de confinement. La structure est constituee par une enceinte de confinement se composant d'une jupe cylindrique et d'un dome et par un batiment couronne entourant l'enceinte de confinement. Le batiment couronne se compose d'une jupe cylindrique et d'une toiture, l'enceinte de confinement et le batiment couronne s'elevant sur un radier general commun. Des structures internes sont positionnees a l'interieur de l'enceinte de confinement. La toiture du batiment couronne est de forme tronconique ou torique et est encastree dans la jupe cylindrique de l'enceinte de confinement. Les structures internes sont desolidarisees de l'enceinte de confinementOriginal Title
Structure de batiment reacteur comportant une toiture de batiment couronne encastree dans la jupe cylindrique de l'enceinte de confinement
Primary Subject
Source
13 Aug 1982; 11 p; FR PATENT DOCUMENT 2499751/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] The rule applies to the fabrication of safety containments of steel for stationary lightwater reactors including the supports connected with the safety containment, as well as for pressure-bearing parts of transfer canals. (orig./HP)
[de]
Die Regel gilt fuer die Herstellung von Sicherheitsbehaeltern aus Stahl fuer ortsfeste Leichtwasserreaktoren einschliesslich der mit dem Sicherheitsbehaelter fest verbundenen Stutzen und fuer drucktragende Teile von Schleusen. (orig./HP)Original Title
Reaktorsicherheitsbehaelter aus Stahl
Primary Subject
Source
Jun 1983; 68 p; Heymanns; Koeln (Germany, F.R.); KTA--3401.3
Record Type
Book
Literature Type
Standard
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] After describing the containment of the PWR power station at Paluel in France, its role is defined. The methods used to limit the global leakage of the internal vessel are then described. To do so, an examination is made of the porosity of the concrete and cracking, concrete repairs and the treatment of repairs by injection in those areas where air tests have revealed the presence of leaks
[fr]
Apres une description de l'enceinte de confinement de la centrale PWR de Paluel en France, on definit son role. Puis on expose les moyens mis en oeuvre pour limiter le taux de fuite globale de l'enceinte interne; pour cela on examine la porosite du beton et la fissuration, les reprises de betonnage et le traitement des reprises par injection dans les zones ou les essais a l'air ont revele des fuitesOriginal Title
Enceintes de confinement des batiments reacteurs 1300 MW de Paluel; France
Primary Subject
Source
Contribution of nuclear engineering to building techniques; Paris, France; 21 May 1980
Record Type
Journal Article
Literature Type
Conference
Journal
Annales de l'Institut Technique du Batiment et des Travaux Publics; ISSN 0020-2568;
; (no.397); p. 171-178

Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Short communication
Primary Subject
Record Type
Journal Article
Journal
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] In this paper containment buildings of 1300 MW PWR are examined: how concrete is put into position and tests with pressurized air for verification of tightness
[fr]
On examine les enceintes des reacteurs de 1300 MW, la mise en place du beton et les essais en air sous pression pour verifier le taux de fuiteOriginal Title
Etancheite des betons, permeabilite a l'air, essais et methodes de controle; PWR
Primary Subject
Source
Contribution of nuclear engineering to building techniques; Paris, France; 21 May 1980
Record Type
Journal Article
Literature Type
Conference
Journal
Annales de l'Institut Technique du Batiment et des Travaux Publics; ISSN 0020-2568;
; (no.397); p. 114-118

Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The principal purpose of the SAREF Reactor Containment Building (RCB) is to prevent the uncontrolled release of radioactive materials to the atmosphere as a result of accidental occurrences inside the containment. The RCB houses numerous reactor systems and components including the Prestressed Concrete Reactor Vessel (PCRV). The design of the RCB is of reinforced concrete (steel-lined). The containment building is embedded nearly 100 feet in lava rock. It has therefore been necessary to independently formulate an appropriate and conservative design approach
Primary Subject
Source
Dec 1975; 134 p; Available from NTIS., PC A07/MF A01
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Estimates of the rate of heat removal from the containment atmosphere following a loss of colant accident (LOCA) are important to the prediction of containment peak pressure and temperature which are essential parameters in designing the containment building. An overall survey and discussion of mechanisms, experimental results, empirical correlations and analytical models that are relevant to the heat transfer inside the containment have been made. As a result of this review, the current state of the konwledge about the containment heat transfer can be understood and it is known that more investigations are needed to avoid the misuse of various correlations. (Author)
Primary Subject
Record Type
Journal Article
Journal
Journal of the Korean Nuclear Society; ISSN 0372-7327;
; v. 15(2); p. 123-134

Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
James, E.B.; Farabee, O.A.; Bliss, R.J.
Hanford Engineering Development Lab., Richland, WA (USA)1978
Hanford Engineering Development Lab., Richland, WA (USA)1978
AbstractAbstract
[en] The initial Integrated Leak Rate Test (ILRT) of the Fast Flux Test Facility containment building was performed from May 27 to June 2, 1978. The test was conducted in air with systems vented and with the containment recirculating coolers in operation. 10 psig and 5 psig tests were run using the absolute pressure test method. The measured leakage rates were .033% Vol/24 hr. and -.0015% Vol/24 hrs. respectively. Subsequent verification tests at both 10 psig and 5 psig proved that the test equipment was operating properly and it was sensitive enough to detect leaks at low pressures. This ILRT was performed at a lower pressure than any previous ILRT on a reactor containment structure in the United States. While the initial design requirements for ice condenser containments called for a part pressure test at 6 psig, the tests were waived due to the apparent statistical problems of data analysis and the repeatability of the data itself at such low pressure. In contrast to this belief, both the 5 and 10 psig ILRT's were performed in a successful manner at FFTF
Primary Subject
Source
1978; 18 p; ANS meeting; Washington, DC, USA; 12 - 17 Nov 1978; CONF-781105--92; Available from NTIS., PC A02/MF A01
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] A material access lock as defined by this standard is a pressure-resistant and technically gas-tight hollow body connected with the containment and which has got two gates, the inner one of which connects the lock chamber with the interior of the containment and the outer one of which connects the lock chamber with the exterior. It serves exclusively for transferring material or objects. (orig.)
[de]
Eine Materialschleuse im Sinne dieser Regel ist ein mit dem Sicherheitsbehaelter verbundener druckfester und technisch gasdichter Hohlkoerper mit zwei Toren, dessen Innetor den Schleusenraum mit dem Innenraum, des Sicherheitsbehaelters und dessen Aussentor den Schleusenraum mit dem Aussenraum verbindet. Sie dient ausschliesslich zum Schleusen von Material oder Gegenstaenden. (orig.)Original Title
Schleusen am Reaktorsicherheitsbehaelter von Kernkraftwerken. Materialschleusen
Primary Subject
Source
KTA--3409
Record Type
Journal Article
Literature Type
Standard
Journal
Bundesanzeiger; v. 31(137); p. 1-2
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Harstead, G.A.; Morris, N.F.; Unsal, A.I.
Transactions of the 7. international conference on structural mechanics in reactor technology. Vol. J1983
Transactions of the 7. international conference on structural mechanics in reactor technology. Vol. J1983
AbstractAbstract
[en] The stability analysis for a steel containment shell is presented herein. The containment is a freestanding shell consisting of a vertical cylinder with a hemispherical dome. It is stiffened by large ring stiffeners and relatively small longitudinal stiffeners. The containment vessel is subjected to both static and dynamic loads which can cause buckling. These loads must be combined prior to their use in a stability analysis. The buckling loads were computed with the aid of the ASME Code case N-284 used in conjunction with general purpose computer codes and in-house programs. The equations contained in the Code case were used to compute the knockdown factors due to shell imperfections. After these knockdown factors were applied to the critical stress states determined by freezing the maximum dynamic stresses and combining them with other static stresses, a linear bifurcation analysis was carried out with the aid of the BOSOR4 program. Since the containment shell contained large penetrations, the Code case had to be supplemented by a local buckling analysis of the shell area surrounding the largest penetration. This analysis was carried out with the aid of the NASTRAN program. Although the factor of safety against buckling obtained in this analysis was satisfactory, it is claimed that the use of the Code case knockdown factors are unduly conservative when applied to the analysis of buckling around penetrations. (orig.)
Primary Subject
Source
Commission of the European Communities, Luxembourg; 543 p; ISBN 0444 86697 3;
; 1983; p. 277-284; North-Holland; Amsterdam (Netherlands); 7. international seminar on computational aspects of the finite element method (CAFEM-7) in conjunction with the 7. international conference on structural mechanics in reactor technology (SMIRT-7); Chicago, IL (USA); 22-26 Aug 1983; Also published in Nucl. Eng. Des. (May 1983) v. 75(2) p. 303-318.

Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
1 | 2 | 3 | Next |