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AbstractAbstract
No abstract available
Original Title
Experimentelle Untersuchungen zur Waerme- und Stroemungstechnik von Schnellbrueter-Kernelementen
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1972; 19 p; Experts meeting on the present state and requirements of the prediction of physical parameters for thermal and fast power reactors; Juelich, F.R. Germany; 23 Jan 1973; 10 figs.; 18 refs. With abstract in English.
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Report
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Conference
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AbstractAbstract
No abstract available
Original Title
Ein Beitrag zur Auslegung von Karbidbrennstaeben
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Deutsches Atomforum e.V., Bonn (F.R. Germany); p. 354-357; 1973; ZAED; Leopoldshafen, F.R. Germany; Reactor meeting; Karlsruhe, F.R. Germany; 10 Apr 1973; 8 figs.; 8 refs. Short communication only.
Record Type
Book
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Conference
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Kummerer, K.; Geithoff, D.; Weimar, P.
Kernforschungszentrum Karlsruhe (F.R. Germany). Projekt Schneller Brueter
Kernforschungszentrum Karlsruhe (F.R. Germany). Projekt Schneller Brueter
AbstractAbstract
No abstract available
Original Title
Auslegung, Bestrahlung und Nachuntersuchung des UO2-PuO2-Brennstab-Buendels Mol-7A
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Source
Nov 1972; 171 p; 29 tabs.; 23 refs.; with figs. With abstract in German and English.
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Report
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ACTINIDE COMPOUNDS, ANALOG SYSTEMS, CRYSTAL STRUCTURE, ENRICHED URANIUM REACTORS, FUEL ASSEMBLIES, FUEL ELEMENTS, FUNCTIONAL MODELS, IRRADIATION REACTORS, ISOTOPES, MATERIALS TESTING REACTORS, OXIDES, PLUTONIUM COMPOUNDS, REACTOR COMPONENTS, REACTORS, SIMULATORS, TANK TYPE REACTORS, TESTING, THERMAL REACTORS, TRANSURANIUM COMPOUNDS, URANIUM COMPOUNDS, URANIUM OXIDES, WATER COOLED REACTORS, WATER MODERATED REACTORS
Publication YearPublication Year
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Polcer, J.; Barratt, R.O.; Musterer, A.E.
Foster Wheeler Corp., Livingston, N.J. (USA)
Foster Wheeler Corp., Livingston, N.J. (USA)
AbstractAbstract
No abstract available
Original Title
Natriumopvarmet dampgenerator
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Source
2 Mar 1972; 12 p; DK PATENT DOCUMENT 974/72/A/; Publ. 27 Nov 1972; Priority date 2 Mar 1971, USA.
Record Type
Patent
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AbstractAbstract
No abstract available
Original Title
Dispositif de support de faisceaux de tubes enroules en helice suivant plusieurs nappes cylindriques coaxiales
Primary Subject
Source
05 Jan 1971; 15 p; FR PATENT DOCUMENT 2121348/A/
Record Type
Patent
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Hensolt, T.; Rau, P.
Kraftwerk Union A.G., Muelheim an der Ruhr (Germany, F.R.)
Kraftwerk Union A.G., Muelheim an der Ruhr (Germany, F.R.)
AbstractAbstract
[en] The ventilated fuel pins of the gas cooled Fast Breeder are fixed at a pin supporting plate. The fastening is realized by end caps with a hexagonal form being screwed on the fuel pins. Moreover, they are provided with an outside screw thread with greater or opposing pitch than the inside thread. Thus the orientation of the angle of rotation of a pin can be adjusted without sealing problems. (RW)
[de]
Die ventilierten Brennstaebe des gasgekuehlten SB sind an einer Stabhalteplatte befestigt. Die Befestigung erfolgt mittels Endkappen, die auf die Brennstaebe aufgeschraubt sind und aussen eine Sechskantflaeche aufweisen. Weiterhin besitzen sie ein Stufengewinde mit groesserer oder gegensinniger Steigung wie das Innengewinde. Somit kann die Drehwinkelorientierung der einzelnen Brennstaebe ohne Schwierigkeiten fuer die Abdichtung eingestellt werden. (RW)Original Title
Brennelement fuer gasgekuehlte Kernreaktoren
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Source
26 Feb 1981; 4 p; DE PATENT DOCUMENT 2756667/C/; Available from Deutsches Patentamt, Muenchen, Germany, F.R
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Patent
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Ballve, H.; Graca, M.C.; Fernandez y Fernandez, E.; Carajilescov, P.
Pontificia Univ. Catolica do Rio de Janeiro (Brazil). Dept. de Engenharia Mecanica
Pontificia Univ. Catolica do Rio de Janeiro (Brazil). Dept. de Engenharia Mecanica
AbstractAbstract
[en] The fuel element of a LMFBR nuclear reactor consists of a wire wrapped rod bundle with triangular array with the coolant flowing parallel to the rods. Using this type of element with seven rods conected to an air open loop. The hydrodinamics behavior of the flow for p/d = 1.20 and l/d = 15.0, was simulated. Several measurements were performed in order to obtain the static pressure distribution at the walls of the hexagonal duct, for Reynolds number from 4.4x103 to 48.49x103 and for different axial and transverse positions, in a wire wrap lead. The axial pressure drop was obtained and determined the friction factor dependence with the Reynolds number. From the obtained results, it was observed the non-dependency of the non-dimensionalized axial and transverse local static pressure distribution at the wall of the hexagonal duct, with the Reynolds number. The obtained friction factor is compared to the results of previous works. (Author)
[pt]
O elemento combustivel de um reator nuclear do tipo LMFBR consiste em um feixe de barras de arranjo triangular com espacadores helicoidais, com o refrigerante escoando entre as barras. Neste trabalho, utilizando-se de tal elemento combustivel composto de sete barras, acoplado a um circuito aberto de ar, foi simulado o comportamento hidrodinamico do escoamento para p/d = 1,20 e l/d = 15,0. Uma serie de medidas foi efetuada para se obter a distribuicao da pressao estatica nas paredes do duto hexagonal, para numeros de Reynolds de 4,4x103 a 48,49x103, variando-se a dependencia do coeficiente de atrito com o numero de Reynolds. Dos resultados obtidos, observou-se a nao-dependencia da distribuicao axial e transversal adimensionalizada da pressao estatica local na parede do duto hexagonal, com o numero de Reynolds. O coeficiente de atrito obtido e comparado com os resultados de trabalhos anteriores. (Autor)Original Title
Medidas da pressao estatica periferica e da queda de pressao em um feixe de barras de arranjo triangular com espacadores helicoidais
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Source
Jul 1981; 103 p
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Report
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Maschek, W.; Froehlich, R.
Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Neutronenphysik und Reaktortechnik; Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter
Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Neutronenphysik und Reaktortechnik; Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter
AbstractAbstract
[en] In the framework of the licensing process for SNR-300 recriticalities and secondary excursions have been analyzed for severe hypothetical loss of flow accidents. The energetics of secondary excursions, which can be triggered by different conceivable forms of recriticality as the collapse of boiling fuel/steel pools or the reentry of previously ejected core material into high material worth regions, have been estimated and upper bounds are given on the basis of various model cases. The results of this bounding case study show that the maximum mechanical energy releases (determined by expansion of the hot fuel vapor to the stretched cover gas volume of SNR-300) yield with superposition of numerous pessimistic assumptions concerning modelling and parameters about 100 MJ. (orig.)
[de]
Im Rahmen des Genehmigungsverfahrens fuer den SNR-300 wurde fuer schwere hypothetische Kuehlmitteldurchsatzstoerfaelle das Auftreten und der Verlauf von Rekritikalitaeten bzw. von Sekundaerexkursionen untersucht. Auf der Basis verschiedener Modellfaelle wird im Sinne einer Grenzfallbetrachtung die Energetik von Sekundaerexkursionen abgeschaetzt, welche durch verschiedene denkbare Rekritikalitaetsformen, wie z.B. durch das Kollabieren eines siedenden Brennstoff/Stahlpools oder den Wiedereintritt von vorher ejeziertem Kernmaterial in Bereiche hohen Materialwertes, ausgeloest werden koennen. Die Ergebnisse dieser Grenzfall-Untersuchungen zeigen, dass die maximalen mechanischen Energiefreisetzungen (bestimmt durch Expansion des heissen Brennstoffdampfes auf das gedehnte Schutzgasvolumen des SNR-300) bei Ueberlagerung von zahlreichen pessimistischen Annahmen bzgl. Modellierung und Parameterwahl bei etwa 100 MJ liegen. (orig.)Original Title
Untersuchung von Modellfaellen fuer Sekundaerkritikalitaeten im Kernbereich des SNR-300 (Mark 1A Kern)
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Source
Apr 1982; 142 p
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Report
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Cabrillat, J.C.; Clauzon, P.; Dufour, P.
CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-les-Durance (France)
CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-les-Durance (France)
AbstractAbstract
[en] The value of the annual flow of fissile mixed oxide passing through the plants of the fabrication-reprocessing cycle has a preponderant effect on the cost of the fuel cycle of fast reactors. This annual flow can be reduced either by increasing the performance of the fuel elements or by using new core concepts. It is this latter possibility that is examined in this paper using a steel atom displacement criterion as criterion for the end of life of fuel assemblies. The facts provided should make it possible to guide the choice of core concept of the reactors built after Super Phenix in order to improve on the cost of the fuel cycle of fast reactors
[fr]
La valeur du flux annuel d'oxyde mixte fissile passant dans les usines du cycle (fabrication - retraitement) a une influence preponderante sur le cout du cycle de combustible des Reacteurs a Neutrons Rapides. Ce flux annuel peut etre reduit soit en augmentant les performances des elements combustibles, soit en utilisant de nouveaux concepts de coeur; cette derniere possibilite est examinee dans ce papier en se fixant un critere en DPA (Deplacement par Atome d'Acier) comme critere de fin de vie des assemblages combustibles. Les elements fournis devraient permettre d'orienter le choix du concept de coeur des Reacteurs construits apres Super Phenix afin d'ameliorer le cout du cycle du combustible des reacteurs a neutrons rapidesOriginal Title
Impact du concept de coeur sur le cycle de combustible des reacteurs a neutrons rapides
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Source
Nov 1981; 11 p; International conference on fast neutron reactor fuel cycles; London, UK; 9 - 13 Nov 1981
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Report
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Conference
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AbstractAbstract
[en] For the intermediate storage of KNK II-fuel in water, Kraftwerk Union AG designed a 'wet storage facility for KNK II-fuel' by order of Kernforschungszentrum Karlsruhe. This wet storage facility is designed as At Reaktor (AR) storage by what the existing infrastructure of KNK II and KfK can be used. The storage of the fuel elements takes place in one storage pool equipped with compact storage racks. The maximum storage capacity is 10 cores of the KNK II. Cooling of the pool water is performed by a cooling system with natural recirculation which transfers the decay heat to the surrounding air. (orig.)
[de]
Zur Zwischenlagerung von KNK II-Brennelementen unter Wasser erstellte die Kraftwerk Union AG die Konzeptstudie 'Nasslager fuer KNK II-Brennelemente' im Auftrag des Kernforschungszentrums Karlsruhe. Dieses Nasslager wurde an die KNK II angebunden konzipiert, wodurch die bestehende Infrastruktur der KNK II und des KfK genutzt werden kann. Die Lagerung erfolgt in einem mit Kompaktlagerstellen ausgeruesteten Lagerbecken mit einer Lagerkapazitaet von 10 KNK II- Kernladungen. Die Kuehlung des Beckenwassers erfolgt ueber ein im Naturumlauf arbeitendes Kuehlsystem, welches die Nachzerfallswaerme an die Aussenluft abgibt. (orig.)Original Title
Konzeptstudie zur Zwischenlagerung von KNK II-Brennelementen unter Wasser
Primary Subject
Source
Marth, W.; Lahr, H.; Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter; 183 p; Mar 1982; p. 157-164; Seminar on technological questions of the breeder fuel cycle; Karlsruhe, Germany, F.R; 15 Oct 1981
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