Component Category: --Fuel and cladding
10 documents found
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Transfer functions between the central fuel temperature, the cladding temperature and the power of fuel assemblies Uebertragungsfunktionen zwischen der zentralen Brennstofftemperatur und der Huellrohrtemperatur sowie der Leistung von Brennelementen
Ferranti, P.;Mitzel, FKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-INR--01.24.9/3 - German - 1977
Abstract: For the analysis of experiments, in which the heat transfer between fuel and cladding shall be deduced from the variations of the central fuel temperature, the surrounding cladding temperature and the power, the transfer functions between these parameters are required. They have been calculated in the frame of a formerly applied model. The provision of a special version of an existing computer program allowed the numerical calculation. Input data description and test sample are given
Key words: boiling detection;calculation methods;fuel elements;heat transfer;in core instruments;knk-2 reactor;temperature monitoring;transfer functions
R&D Category: -Analytic and numeric methods
display the document: 34087742.pdf
The irradiation of carbide fuel pins in the frame of the Fast Breeder Project Die Bestrahlung von Karbid-Brennstaeben im Rahmen des PSB
Steiner, HKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.03.03P23C - German - 1979
Abstract: The report gives an overview of the present status and the most important results of the carbide-program of the Fast Breeder Project PSB. Only integral fuel pin irradiation experiments are considered. The PSB-program is characterized by a plurality of parameter variations, partly within large ranges. The most important variations concern the concept of the bonding, the smear- and pellet-density, the fabricated gap width between fuel and cladding as well as the irradiation conditions for the pin power, cladding temperature and burnup. In view of the small number of test samples the inclusion of the international irradiation experience is a great advantage. The results with the gas-bonded fuel pins indicate, that the achievable burnup increases when the smear density is decreased from 85 % to 80 %. Burnups of 7 % and more together with linear powers of 800 - 1100 W/cm can only be reached with smear densities of 80 % or less. For sodium-bonded pins, the defect-rate is smaller than for gas-bonded pins. Out of the four observed defects two were caused by failures of the capsule and the others by excessive cladding carburization. Besides questions of concept valuation, the present report also discusses some important aspects of the irradiation behavior of carbide samples, such as thermal behavior and mechanical interaction between fuel and cladding and carburization
Key words: burnup;carburization;cladding;fuel pellets;irradiation;knk-2 reactor;mixed carbide fuels;physical radiation effects
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34086300.pdf
Fuel reprocessing of the first failed KNK-II fuel element in MILLI. Die Wiederaufarbeitung von Brennstoff aus dem ersten defekten KNK II-Brennelementen in der MILLI
Bleyl, H.J. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Heisse Chemie)KFK--3278 - German - 1982
Abstract: In MILLI reprocessing of fuel from 32 KNK II-pins was carried out. 3 extraction cycles were applied: co-decontamination, U-/Pu-separation and purification of uranium. The products were shipped to refabrication of KNK II fuel by Nukem and Alkem companies. (orig.)
Key words: fuel element failure;fuel pins;knk-2 reactor;purex process;solvent extraction
R&D Category: Decontamination, decommissioning, disassembly
display the document: 13695220.pdf
Experience on fuel recycling. Erfahrungen zur Brennstoff-Rezyklierung
Schneider, V.;Druckenbrodt, W.G. (Alpha Chemie und Metallurgie G.m.b.H.)KFK--3278 - German - 1982
Abstract: The plutonium of the second generation out of the KNK-reactor will be converted at the fuel fabrication by ALKEM by the Au/PuC process. The preliminary tests for the fabrication have been finished and two batches were converted. Up to now the results show no principal difficulties. (orig.)
Key words: fuel fabrication plants;knk-2 reactor;plutonium recycle
R&D Category: Decontamination, decommissioning, disassembly
display the document: 13695223.pdf
Assays on homogeneity of the mixed oxide at various stages of the fuel cycle. Untersuchungen zur Homogenitaet des Mischoxids in verschiedenen Stadien des Brennstoffkreislaufs
Kleykamp, H. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Material- und Festkoerperforschung 1 - Teilinstitut Kernbrennstoffe);Pejsa, R. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Hauptabteilung Kerntechnische Betriebe)KFK--3505 - German - 1983
Abstract: The uranium/plutonium and oxygen/metal homogeneities are measured fro KNK II/1 standard mixed oxides and for AUPuC mixed oxides irradiated in the FR 2-Vg. 7/II experiment within the different stages of the fuel cycle. The U-Pu distribution in unirradiated pellets, in irradiated pins and in the undissolved fraction of the fuel after the reprocessing is measured in standart mixed oxides. The concentration and the distribution of the plutonium in the blankets of pins from different irradiation experiments are given. For the AUPuC mixed oxides are determined in particular the oxigen distribution of after-oxidized unirradiated pellets, the fuel relocation and the formation of new phases in irradiated pins, and the composition of the residues from the dissolution of the fuel. (orig.)
Key words: fuel cycle;homogenization methods;knk-2 reactor;mixed oxide fuels;plutonium dioxide;uranium dioxide
R&D Category: any or undefined
display the document: 15028662.pdf
Development of materials for higher burn-up rates. Werkstoffentwicklung fuer hoehere Abbraende
Ehrlich, K.;Anderko, K. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Material- und Festkoerperforschung 2 - Teilinstitut Huellwerkstoffe)KFK--3505 - German - 1983
Abstract: The results obtained so far concerning both high-nickel austenitic steels (X10CrNiMoTiB10 25) and ferritic-martensitic steels (X18CrMoVNb12 1 corresponds to 1.4914) justify the expectations placed in these materials. Future R and D work will concentrate on high-nickel austenitic steels, in particular on in-pile residence time in the range of maximum cladding mean temperatures (He embrittlement), on confirmation of the fairly good swelling and creep behaviour to be obtained from neutron irradiation experiments as well as on material qualification and technology. As far the development in the field of martensitic steels the major question concerns the influence of neutron irradiation on the transient temperature. It is just as important and interesting to detect and describe the ruling in-pile creep mechanism in the 400 to 6000C range. Furthermore, questions on the fabrication and qualification of cladding tube boxes are also preeminent. (orig.)
Key words: austenitic steels;burnup;fbr type reactors;fuel cans;knk-2 reactor;martensitic steels;reactor materials
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 15028667.pdf
Behavior of the core coolant outlet temperatures of KNK II. Performed investigations, summary of the results and present status of knowledge Verhalten der Kuehlmittelaustrittstemperaturen beim Kern KNK II/2. Durchgefuehrte Untersuchungen, Zusammenfassung der Ergebnisse und gegenwaertiger Kenntnisstand
Finke, GKernkraftwerk-Betriebsgesellschaft mbH (Germany)
KBG--BL1/86 - German - 1986
Abstract: The coolant outlet temperatures of the Mark II test zone fuel assemblies of the second core of KNK II started to rise slowly about 20 equivalent full-power days (efpd) after their start-up. After about 100 efpd the increase came to saturation, having reached values of 20 to 30 K. From May to August 1984 the plant was shutdown for the replacement of different experimental facilities, and after restart the temperature rises were about halved, but reached their original level during the following operation. Also a fresh assembly, which had to replace a defective one after 280 efpd, showed the same phenomenon, i.e. similar increase with similar speed. During a shutdown phase from October 1985 until March 1986 different experiments were performed at the plant, and in parallel to that out-of-pile experiments and theoretical investigations were performed to clarify the phenomenon. The explanation of the temperature drifts has to be seen in impurities in the sodium, which deposit on the surface of the fuel claddings and the pin spacers, thus leading to an increased surface roughness and thermohydraulic resistance in the fuel assemblies. Additionally, larger particles or agglomerates of smaller ones could deposit on the grid spacers causing a partial blockage of the free flow area. Since the deposits do not stick firmly to the surface, they are partly removed by the flowing sodium, so that the saturation effect of the temperature increase could be explained. These explanations are being supported by experiences gathered in foreign plants
Key words: cladding;deposits;friction;fuel assemblies;knk-2 reactor;reactor fueling;reactor operation;roughness;spacers;temperature distribution;temperature measurement;thermal hydraulics
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34087731.pdf
Post examinations of fuel pins of the KNK II fuel element NY-308 with Niobium coating Nachuntersuchungen von Niob-innenbeschichteten Brennstaeben aus dem KNK II/2 Brennelement NY-308
Patzer, G.;Hess, BINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.07318.7 - German - 1987
Abstract: In the fuel assembly NY-308 of the second core of KNK II two fuel pins with a Niobium coating on the inner cladding surface underwent post-irradiation examinations, one of them a destructive one. The examinations demonstrated a getter-effect of the Nb-layer, which did influence the axial Cesium distribution, especially in the upper part of the fuel column. Additionally, the inner cladding corrosion was prevented successfully. On the Nb-layer itself mechanical attacks and changes, like peel-off or chip-off effects, were found. These did however not influence the effectiveness of the Nb-layer obviously. Investigations on other fuel pins with Nb-coated claddings and much higher fuel burnup, which are still being irradiated, are promising further knowledge
Key words: cladding;corrosion;fuel assemblies;fuel pins;knk-2 reactor;niobium;performance testing;post-irradiation examination;surface coating
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34085723.pdf
Results of tests with open fuel in KNK II Ergebnisse des Einsatzes freier Brennstofftestflaechen in der KNK II
Schmitz, GKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.17P56B - German - 1987
Abstract: For the operation of Liquid Metal Cooled Fast Breeder Reactors with cladding failures the consequences of increased contamination by fission products and fuel and the possibility of failure propagation to adjacent fuel pins due to fuel swelling have to be envisaged. To clarify some of these problems a KNK II test program involving open fuel was defined with the first experiments of this program being performed between October 1981 and May 1984. After the description of the test equipment and of the test program, the results will be presented on delayed neutron measurements, fission gas measurements and post irradiation examinations. The report will conclude with a discussion of the results
Key words: contamination;defects;delayed neutron analysis;failures;fission product release;fuel element failure;knk reactor;knk-2 reactor;testing
R&D Category: Safety aspects
display the document: 34086286.pdf
Post-irradiation examinations and theoretical analyses of the fuel and fuel pin behavior of innovative systems. Bestrahlungsnachuntersuchungen und modelltheoretische Analysen zum Brennstoff- und Brennstabverhalten innovativer Systeme
Ernst, W.;Freund, D.;Geithoff, D.;Heck, M.;Jacobi, O.;Steiner, H.;Weimar, PFZKA--5600 - German - 1995
Abstract: For the development of LMR cladding materials an irradiation test was performed in the KNK II reactor between 1986 and 1991. It demonstrated that a temperature gradient in the cladding has no observable effect on swelling behavior. PIEs of transient experiments in the Petten HFR have shown no significant cladding deformations. (orig.)
Key words: fuel cans;knk-2 reactor;post-irradiation examination;reactor safety experiments;transients
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 28005773.pdf