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Bouyssie, C.; Giraud, J.P.; Dulac, J.; Chauvel, D.
Transactions of the 8. international conference on structural mechanics in reactor technology. Vol. F1 and F21985
Transactions of the 8. international conference on structural mechanics in reactor technology. Vol. F1 and F21985
AbstractAbstract
[en] In french nuclear PWR power plants, water steam high energy pipes run along the electrical and reactor buildings. In order to protect these safety buildings we have chosen to restrict the displacements of the pipes in case of breaking by the settlement of anti-whip structures. To design these structures and to better evaluate the impact force pipe and R.C. structures, experiments on straight sections pipe crushing have been carried out. These static and dynamic tests have allowed us to evaluate the impact force and to perform the design of anti-whip structures by considering the energy absorbing properties of the pipe itself. (orig.)
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Stalpaert, J. (ed.); Commission of the European Communities, Luxembourg. Directorate General Information Market and Innovation; 547 p; ISBN 0444 86960 3; ; 1985; p. 145-149; North-Holland; Amsterdam (Netherlands); 8. international conference on structural mechanics in reactor technology (SMIRT-8); Brussels (Belgium); 19-23 Aug 1985
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AbstractAbstract
[en] EDF has initiated a research program on the non linear behaviour of RC slabs subjected to short time loads, such as soft missiles. This program includes an experimental part and a theoretical analysis to simulate, through computation models, the behaviour of tested plates and try to deduce some pratical rules for plastic design. The ultimate purpose is to show that it is possible to drastically reduce the bending reinforcement of anti-missile slabs without fearing failure or even large deflection. We present in this paper the first test results regarding accidental loads due to small aircrafts (LEAR JET or CESSNA). (orig./HP)
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Societe Francaise d'Energie Nucleaire (SFEN), 75 - Paris; Commission of the European Communities, Brussels (Belgium); 255 p; ISBN 0 444 86262 5; ; 1981; vp; North-Holland Publishing Co; Amsterdam, Netherlands; 6. international conference on structural mechanics in reactor technology; Paris, France; 17 - 21 Aug 1981
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Book
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Pouyet, P.; Picaut, J.; Costaz, J.L.; Dulac, J.
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 method described is used to test failure mechanisms and to calculate the corresponding ultimate loads. The main advantages it offers are simple modelling, the possibility of representing all the prestressing and reinforcement steels simply and correctly, and fewer degrees of freedom, hence lower cost (the program can be run on a microcomputer). However, the model is sensitive to the arrangement of the interface elements, presupposing a given failure mechanism. This normally means testing several different models with different kinematically possible failure patterns. But the ease of modelling and low costs are ideal for this type of approach. (orig./RW)
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Commission of the European Communities, Luxembourg; 543 p; ISBN 0444 86697 3; ; 1983; p. 113-119; 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
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Book
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Avet-Flancard, R.; Barbe, B.; Costaz, J.L.; Dulac, J.
5th international meeting on thermal nuclear reactor safety. Proceedings. Vol. 21984
5th international meeting on thermal nuclear reactor safety. Proceedings. Vol. 21984
AbstractAbstract
[en] Studies on the behaviour of reactor containments under off-design conditions have been conducted in France on both 900 MW PWR with metallined containments and 1300 MW PWR with dual concrete wall containments. The results show that: 900 MW PWR containments should keep their intergrity until failure since the risks of metal liner tearing are low; the behaviour of 1300 MW PWR containments is governed by the transverse carcking of the concrete which, due to the resulting leakage rate, tends to control internal pressure to a value less than collapse pressure and mechanical penetrations exhibit a mechanical strength which is well above containment collapse pressure. (orig./HP)
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Bork, G.; Rininsland, H. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Nukleare Sicherheit); Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.); 664 p; Dec 1984; p. 1322-1326; 5. international meeting on thermal nuclear reactor safety; Karlsruhe (Germany, F.R.); 9-13 Sep 1984
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Report
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Bianchini, J.C.; Dubois, J.J.; Avet-Flancart, R.; Dulac, J.
Structural mechanics in reactor technology. Vol. J(a)1981
Structural mechanics in reactor technology. Vol. J(a)1981
AbstractAbstract
No abstract available
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Source
Societe Francaise d'Energie Nucleaire (SFEN), 75 - Paris; Commission of the European Communities, Brussels (Belgium); 325 p; ISBN 0 444 86261 7; ; 1981; vp; North-Holland Publishing Co; Amsterdam, Netherlands; 6. international conference on structural mechanics in reactor technology; Paris, France; 17 - 21 Aug 1981; Published in summary form only.
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Book
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Conference
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Barbe, B.; Avet-Flancard, R.; Perrot, J.; Berriaud, C.; Dulac, J.
Structural mechanics in reactor technology. Vol. J(b)1981
Structural mechanics in reactor technology. Vol. J(b)1981
AbstractAbstract
[en] The aims of this study are to obtain experimental data and theoretical evaluation of the transient field pressure existing on importants buildings of the plant. The knowledge of the pressure loading permits then to predict the structure mechanical behaviour. For this purpose the cylindrical reactor building and the parallelepipedic fuel building have been modelized to a 1/40 scale. These models were realized as carefully as possible with prestressing in the thickness of microconcrete walls and were submitted to incident shock waves obtained by T.N.T. explosions. Several characteristics explosion directions have been tested. Experimental data were recorded with pressure and displacement transducers and also by accelerometers. The results show that: 1) the geometrical dihedral between reactor and fuel building induces local overpressures five times the incident pressures; 2) no apparent damage occurred on the structure, for the range of field pressure tested so far; this may related to only small effects of resonances. Simultaneously a tridimensional, acoustic code has been developed an conveniently correlates experimental data. (orig./HP)
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Source
Societe Francaise d'Energie Nucleaire (SFEN), 75 - Paris; Commission of the European Communities, Brussels (Belgium); 255 p; ISBN 0 444 86262 5; ; 1981; vp; North-Holland Publishing Co; Amsterdam, Netherlands; 6. international conference on structural mechanics in reactor technology; Paris, France; 17 - 21 Aug 1981
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Book
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Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Brochard, J.; Carretero, L.; Combescure, A.; Avet-Flancard, R.; Dulac, J.
Structural mechanics in reactor technology. Vol. J(a)1981
Structural mechanics in reactor technology. Vol. J(a)1981
AbstractAbstract
[en] This paper presents the results of the nonlinear axisymetric analysis of the behaviour of containment buildings (PWR 900 MWe with metallic skin and PWR 1300 MWe without any skin), under LOCA pressure and temperature loadings. The evolutions of pressure and temperature from the accident are the following: increase of pressure 0.3 bar/hour and increase of temperature 20C/hour. This thermomechanical study has been made with the Finite Element Method, and the CEASEMT system code has been used. The objectives of this study have been obtained: - the pressure of the first of concrete - the pressure of trough fracture of concrete - the ruin modes of the containment building However, the spatial discretization of the structure used in this Finite Element analysis induces limitations to the quantitative evaluation of the fracture of concrete, because the informations about fractures are known only on discrete points. From this analysis, we are not able to show up phenomeneon like strain localizations. (orig./HP)
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Societe Francaise d'Energie Nucleaire (SFEN), 75 - Paris; Commission of the European Communities, Brussels (Belgium); 325 p; ISBN 0 444 86261 7; ; 1981; vp; North-Holland Publishing Co; Amsterdam, Netherlands; 6. international conference on structural mechanics in reactor technology; Paris, France; 17 - 21 Aug 1981
Record Type
Book
Literature Type
Conference
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Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Since 1974 CEA and EDF have developed in France a large programme with the aim to work out a means of computation reliable enough for the knowledge of the behaviour of reinforced concrete walls under missile impacts. The shots were performed on reinforced concrete slabs, the thickness of which were chosen to represent in a realistic way the thickness of the wall of a reactor containment. The scales used in this modeling were mainly one-half and one-third. The following parameters were kept constant: the properties of the concrete and the geometric shape of the missile (flat nose). Also studied were the effects of variation of parameters like missile velocity (25-450 m/s), its mass (20-300 kg), ratio of the missile diameter to the thickness of the slab (0.24-2.9) and characteristics of the steel reinforcement. The results of these tests may be summarized in a homogeneous perforation formula in the case of a velocity lower than 200 m/sec: Vsub(c)2=1.7 sigmarhosup(1/3)(sigmae2/M)sup(4/3), where Vsub(c), is the minimum velocity for perforation, phi diameter of the missile, M its mass, sigma the ultimate compressive strength of the concrete, rho its density and e its thickness. (Auth.)
Original Title
Comportement local des enceintes en beton sons l'impact d'un projectile rigide
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4. international conference on structural mechanics in reactor technology; San Francisco, USA; 15 - 19 Aug 1977
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Journal Article
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Conference
Journal
Nuclear Engineering and Design; v. 45(2); p. 457-469
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Berriaud, C.; Sokolovsky, A.; Gueraud, R.; Dulac, J.; Labrot, R.
Structural mechanics in reactor technology1977
Structural mechanics in reactor technology1977
AbstractAbstract
No abstract available
Primary Subject
Source
Jaeger, T.A.; Boley, B.A. (eds.); International Association for Structural Mechanics in Reactor Technology; Commission of the European Communities, Brussels (Belgium); v. J(b) p. J7/9; ISBN 0 444 85062 7; ; 1977; v. J(b) p. J7/9; North-Holland; Amsterdam, Netherlands; 4. international conference on structural mechanics in reactor technology; San Francisco, USA; 15 - 19 Aug 1977; Published in summary form only.
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Book
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AbstractAbstract
[en] Since 1974 C.E.A. and E.D.F. developed in France a large programme with the aim to work out a means of computation reliable enough for the knowledge of the behavior of reinforced concrete walls under missile impacts. In this paper are described the subsequent tests and the interpretation of the whole programme. The shots were performed on reinforced concrete slabs, thickness of which were chosen to represent in a realistic way the thickness of the wall of a reactor containment. The scales used in this modeling were mainly one half and one third. In any case the similarity law used in this work is such to keep the value of velocity unchanged. In a first step the following parameters were kept constant: thickness and properties of the concrete, reinforcement ratio, geometric shape of the missile. On the other hand were studied the effects of variation of parameters like the missile velocity (90 to 200 m/s), the missile diameter (0.2 to 0.3 m) and its mass (20 to 300 kg). Taking into account this first series of tests formulae for computation of a limit perforation velocity, Vsub(e) and of a minimum protection depth, e, were worked out as functions of the characteristics parameters of projectile and wall. In a second step there was tried to define the limits of validity of these formulae in the case of variation of the following parameters: ratio of the missile diameter to the thickness of the slab (0,24 to 2,9), velocity of the missile (25 m/s to 450 m/s), characteristics of the concrete, characteristics of the steel reinforcement, shape of the projectile
[fr]
Depuis 1974, le CEA et l'EDF ont developpe en France un programme important destine a etudier des moyens de calculs assez fiables pour la connaissance du comportement des enceintes en beton sous l'impact d'un projectile. Dans cette communication on decrit les essais effectues et l'interpretation du programme. Les chocs ont ete effectues sur des plaques de beton renforce dont l'epaisseur a ete choisie dans le but de representer d'une maniere realiste, les parois d'un reacteur. Les echelles utilisees pour ces modeles sont de 1/2 et 1/3. En tout cas la loi de similarite utilisee dans ce travail conserve la valeur de la vitesse inchangee. Dans une premiere etape les parametres suivants sont conserves constants: epaisseur et proprietes du beton, forme geometrique du modele. D'autre part on a etudie les effets de variations des parametres comme la vitesse du missile (90 a 200 m/s), le diametre du missile (0,2 a 0,3 m) et sa masse (20 a 300 kg). Prenant en compte cette premiere serie d'essais, les formules pour le calcul d'une vitesse de perforation limite Ve et d'une profondeur de protection minimum e ont ete utilisees comme fonctions des parametres caracteristiques du projectile et de l'enceinte. Dans une seconde etape, on a essaye de definir les limites de validite de ces formules dans le cas de la variation des parametres suivants: rapport du diametre du missile a l'epaisseur de la plaque (0,24 a 2,9), vitesse du missile (25 m/s a 450 ms/), caracteristiques du beton, caracteristiques du renforcement de l'acier, forme du projectileOriginal Title
Comportement local des enceintes en beton sous l'impact d'un projectile rigide
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1977; 21 p; 4. International conference on structural mechanics in reactor engineering; San Francisco, Calif., USA; 15 - 19 Aug 1977; Copies available from Service de Documentation CEN Saclay, BP no.2, 91190 Gif-sur-Yvette (France)
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