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AbstractAbstract
[en] This year's reactor meeting dealt with the present state of fuel element development which is given in about 20 reviews. Besides, a few lectures on the fuel element behaviour in light water reactors (LWR), the investigation results in the fields of the high temperature (HTR) and fast breeder (SR) development gave rise to interesting main topics which are reported here. (orig./LH)
[de]
Die diesjaehrige Reaktortagung beschaeftigte sich in rund 20 Referaten mit dem derzeitigen Stand der Brennelement-Entwicklung. Dabei bildeten neben wenigen Vortraegen ueber das Brennelement-Verhalten in Leichtwasser-Reaktoren (LWR) die Untersuchungsergebnisse aus den Bereichen der Hochtemperatur (HTR)- und der Schnellbrueter (SR)-Entwicklung interessante Schwerpunkte, ueber die hier berichtet wird. (orig./UA)Original Title
Keine Alternative zur Kernenergie
Primary Subject
Source
Reactor conference; Nuernberg, F.R. Germany; 8 Apr 1975
Record Type
Journal Article
Literature Type
Conference
Journal
VDI (Ver. Dtsch. Ing.) Nachr; v. 29(22); p. 2
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Weimar, P.; Zimmermann, H.
Kernforschungszentrum Karlsruhe (F.R. Germany). Inst. fuer Material- und Festkoerperforschung1973
Kernforschungszentrum Karlsruhe (F.R. Germany). Inst. fuer Material- und Festkoerperforschung1973
AbstractAbstract
No abstract available
Original Title
Oxid-Cermet-Brennstaebe: Herstellung, Eigenschaften und Bestrahlungsverhalten
Primary Subject
Source
Aug 1973; 44 p; 28 figs.; 5 tabs.; 12 refs. With abstract in German and English.
Record Type
Report
Report Number
Country of publication
BURNUP, CERMETS, CHROMIUM, CRACKS, DIAGRAMS, ELECTRIC CONDUCTIVITY, FABRICATION, FLEXURAL STRENGTH, FUEL CANS, FUEL PINS, FUEL RODS, GRAIN DENSITY, HASTELLOY X, INCONEL ALLOYS, IRRADIATION CAPSULES, IRRADIATION PROCEDURES, MATERIALS TESTING, MATRIX MATERIALS, MECHANICAL PROPERTIES, MICROSTRUCTURE, MOLYBDENUM, TEMPERATURE DEPENDENCE, URANIUM DIOXIDE, VANADIUM
ACTINIDE COMPOUNDS, ALLOYS, CHALCOGENIDES, CHROMIUM ALLOYS, COBALT ALLOYS, COMPOSITE MATERIALS, CRYSTAL STRUCTURE, ELECTRICAL PROPERTIES, ELEMENTS, FUEL ELEMENTS, HASTELLOYS, HEAT RESISTING ALLOYS, IRON ALLOYS, METALS, MOLYBDENUM ALLOYS, NICKEL ALLOYS, NICKEL BASE ALLOYS, OXIDES, PHYSICAL PROPERTIES, REACTOR COMPONENTS, REACTOR MATERIALS, TESTING, TRANSITION ELEMENTS, TUNGSTEN ALLOYS, URANIUM COMPOUNDS, URANIUM OXIDES
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Kummerer, K.; Weimar, P.
Kernforschungszentrum Karlsruhe (F.R. Germany). Projekt Schneller Brueter; Kernforschungszentrum Karlsruhe (F.R. Germany). Inst. fuer Material- und Festkoerperforschung1975
Kernforschungszentrum Karlsruhe (F.R. Germany). Projekt Schneller Brueter; Kernforschungszentrum Karlsruhe (F.R. Germany). Inst. fuer Material- und Festkoerperforschung1975
AbstractAbstract
[en] Within the fuel pin irradiation experiments in the Karlsruhe Research Reactor FR 2 the Capsule Test Group 5a has a certain special attitude. In the 9 pin specimens of this test group containing UO2-PuO2 fuel the two parameters fuel density and burnup are varied in a specific manner. In order to minimize the disturbing influences of changing irradiation conditions, the density variation was included in every single specimen. In this so-called 'Integrated Density Test' every specimen contained 4 different fuel densities adjacently positioned. Thus, the 4 density stages in one pin were exposed to an identical irradiation history, independent of operational changes in the FR 2. The irradiation was performed in 3 Na/PbBi-capsules - each loaded with 3 pin specimens - at linear rod powers of about 500 W/cm, clad surface temperatures of about 6000C up to the burnup stages 6, 17 and 47 MWd/kg M. The 80 mm long fuel column in every pin was composed by 84, 87, 90 and 93% th.D. fuel portions. The SS cladded pins had an outer diameter of 7 mm. 2 out of the 9 irradiated pins were ruptured, the reason being not definitely known. The documentation in this report presents the objectives of the experiment, the detailed description of design, specification and fabrication of the spin specimens, the irradiation history and the post irradiation examination. The final evaluation demonstrates that structural changes in the fuel are in systematic interconnection to the original fuel density. (orig.)
[de]
Im Rahmen der im Karlsruher Forschungsreaktor FR 2 durchgefuehrten Brennstabbestrahlungsexperimente nimmt die Kapselversuchsgruppe 5a eine gewisse Sonderstellung ein. Bei den 9 mit UO2-PuO2-Brennstoff bestueckten Prueflingen dieser Versuchsgruppe wurden die beiden Parameter Brennstoffdichte und Abbrand in gezielter Weise variiert. Um stoerende Einfluesse des Bestrahlungskanales und des zeitlichen experimentellen Ablaufes moeglichst zurueckzudraengen, fand der Dichtevergleich innerhalb jedes einzelnen Stabprueflings statt. Bei diesem sogenannten 'integrierten Dichteversuch' waren 4 unterschiedliche Brennstoffdichten in jedem Stab uebereinander angeordnet und erlebten so - unabhaengig von eventuellen Betriebsschwankungen des FR 2 - eine identische Bestrahlungsgeschichte. Die Bestrahlung erfolgte in 3 Na/PbBi-Doppelkapseln, in die jeweils 3 Stabprueflinge eingesetzt waren, bis zu Abbraenden von 6.000, 17.000 und 47.000 MWd/t M bei Stableistungen um 500 W/cm und Huelloberflaechentemperaturen um 6000C. Jeder Pruefling hatte eine Brennstoffsaeule von 80 mm Laenge, die sich aus 4 Dichtestufen mit 84, 87, 90 und 93% th.D. zusammensetzte. Die Brennstabhuellen waren aus austenitischem Edelstahl der Werkstoff-Nr. 1.4988, Stabdurchmesser 7 mm, Wandstaerke 0,4 mm. Von den 9 eingesetzten Staeben blieben 7 intakt. Die Schadensursache fuer die beiden anderen Staebe ist nicht bekannt. In der vorliegenden Dokumentation wird nach der Darstellung von Aufgabe und Ziel des Experimentes eine detaillierte Beschreibung der Prueflingsauslegung, der Spezifikationen und der Herstellung, des Bestrahlungsablaufes und der zerstoerungsfreien und zerstoerenden Nachuntersuchung gegeben. Wie die Auswertung zeigt, sind die keramografisch sichtbaren Strukturaenderungen im Brennstoff bereits bei der ersten Abbrandstufe praktisch abgeschlossen. Sie sind in ausgepraegter und systematischer Weise von der Ausgangsdichte des Brennstoffes abhaengig. (orig.)Original Title
Brennstab-Bestrahlungsversuch mit integrierter Variation der Brennstoffdichte
Primary Subject
Secondary Subject
Source
May 1975; 78 p; 28 figs.; 21 tabs.; 11 refs.; with apps.
Record Type
Report
Report Number
Country of publication
CRYSTAL STRUCTURE, FUEL ELEMENTS, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, MATERIALS TESTING, NATURAL URANIUM REACTORS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, TANK TYPE REACTORS, TEST REACTORS, TESTING, THERMAL REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Weimar, P.; Bauer, F.
Kernforschungszentrum Karlsruhe GmbH (Germany)1985
Kernforschungszentrum Karlsruhe GmbH (Germany)1985
AbstractAbstract
[en] Six fuel pins with SNR-300, Mark-Ia fuel in finned tubes with 6 mm outer tube diameter were irradiated in the BR-2 reactor in Mol, Belgium. These pins were irradiated up to 90 MWd/kgHM in the MOL-7D experiment. For three of the six pins destructive examinations were performed in addition to the non-destructive ones. The results of all examinations are presented in this report. They include the fission gas analysis, burnup analysis and ceramography
Original Title
Nachuntersuchungsergebnisse von 3 Brennstaeben des Bestrahlungsexperimentes Mol-7D
Primary Subject
Source
Jun 1985; 78 p; INIS-DE-PSB--081; Country of input: International Atomic Energy Agency (IAEA); Refs, tab, figs
Record Type
Report
Report Number
Country of publication
BREEDER REACTORS, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, FUEL ELEMENTS, IRRADIATION REACTORS, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, MATERIALS TESTING REACTORS, POWER REACTORS, REACTOR COMPONENTS, REACTORS, SODIUM COOLED REACTORS, TANK TYPE REACTORS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Kummerer, K.; Weimar, P.
Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Material- und Festkoerperforschung; Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter1982
Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Material- und Festkoerperforschung; Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter1982
AbstractAbstract
[en] Within the fuel pin development for fast breeder reactors the irradiation experiment Mol-7B comprised the irradiation of a fuel pin bundle with 18 pins in the epithermal neutron flux of the Belgian reactor BR 2. The bundle was loaded in the sodium circuit in the central channel of the BR 2, the so-called IPSL-Loop. The pins contained UO2-PuO2 fuel in a stainless steel cladding. The design of the pins with respect to material composition and geometry were representative for the conditions in a fast breeder prototype like the SNR 300. Having a PuO2-content of about 30 w/o, the smeared density of the fuel was 80% of theoretical density. The claddings consisted of two different types of high temperature resistant stainless steels. The pin diameter was 6.0 mm. The operational conditions during irradiation were designed to be 450 watts/cm for the linear rod power and almost 7000C for the maximum cladding midwall temperature. In the course of the experiment the power happened to be remarkably higher, up to about 590 watts/cm. The target burnup was overdrawn up to 125,000 MWd/t M. After reaching about the half of this burnup the first pin failure in the bundle was revealed by fission gas signals. Nevertheless it was decided to run the experiment beyond breach up to the full irradiation time of 384 days. This report is a documentation of this irradiation experiment, where all data and facts on the experimental objectives, pin design, specifications for pin and bundle, fabrication of the pins including preirradiational tests, the irradiation history, and the destructive and nondestructive post irradiation examination are compiled. Finally an evaluation of the experiment is given and possible reasons for pin failures are discussed. (orig.)
[de]
Der im Rahmen der Brennstabentwicklung fuer schnelle Brutreaktoren durchgefuehrte Bestrahlungsversuch Mol-7B umfasste die Bestrahlung eines Brennstab-Buendels mit 18 Staeben im epithermischen Neutronenfluss des belgischen Reaktors BR 2. Das Stabbuendel war in dem Natrium-Kreislauf im Zentralkanal des BR 2, dem sogenannten IPSL-Loop, eingesetzt. Die Brennstaebe enthielten UO2-PuO2-Brennstoff und Huellmaterial aus Edelstahl. Die Auslegung der Brennstaebe hinsichtlich Materialzusammensetzung und Geometrie stellen eine sehr weitgehende Simulation der Verhaeltnisse in einem Schnellbrueter-Prototyp wie etwa dem SNR-300 dar. Bei einem PuO2-Anteil von 30 Gew.-% betrug die Brennstoffschmierdichte 80% der theoretischen Dichte. Fuer die Stabhuellen kamen zwei verschiedene hochwarmfeste Edelstaehle zum Einsatz. Der Stabdurchmesser war 6,0 mm. Die betriebliche Beanspruchung waehrend der Bestrahlung war mit 450 W/cm maximaler Stableistung und einer maximalen Huellwandtemperatur von knapp 7000C vorgesehen. Die tatsaechlich im Experiment aufgetretene maximale Stableistung lag aber deutlich hoeher, naemlich bei etwa 590 W/cm. Der Zielabbrand wurde betraechtlich ueberzogen, naemlich auf 125000 MWd/t M. Nach Erreichen von ca. 60.000 MWd/t M wurde der erste Stabdefekt im Buendel durch Spaltgassignale bemerkt. Nichtsdestoweniger wurde beschlossen, das Experiment mit dem Defekt ueber die volle Bestrahlungszeit von 384 Tagen zu bestrahlen. Der vorliegende Bericht stellt eine Dokumentation dieses Bestrahlungsversuches dar. In ihr sind alle Einzelheiten ueber die Aufgabenstellung, die Auslegung, Konstruktion und Spezifikation der Staebe und des Buendels, ueber die Stabherstellung, die pruefungen vor der Bestrahlung, die gesamte Bestrahlungsgeschichte sowie ueber die zerstoerungsfreie und zerstoerende Nachuntersuchung der bestrahlten Staebe zusammengestellt. (orig.)Original Title
Das Bestrahlungsexperiment Mol-7B
Primary Subject
Source
Sep 1982; 170 p
Record Type
Report
Report Number
Country of publication
BREEDER REACTORS, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, FUEL ELEMENTS, IRRADIATION REACTORS, LIQUID METAL COOLED REACTORS, MATERIALS, MATERIALS TESTING REACTORS, REACTOR COMPONENTS, REACTORS, TANK TYPE REACTORS, TESTING, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Weimar, P.; Fiedler, H.
Kernforschungszentrum Karlsruhe (F.R. Germany). Inst. fuer Material- und Festkoerperforschung
Kernforschungszentrum Karlsruhe (F.R. Germany). Inst. fuer Material- und Festkoerperforschung
AbstractAbstract
[en] The irradiation was carried out in the helium-loop in the central channel of FR 2. Pins, each with an active length of 150 mm, were irradiated for 3 or 15 days. The whole series consisted of 8 specimens. The plutonium content was some 15 wt percent (rest natural uranium) and the density of pellets was some 86 percent T.D. The cladding was an austenitic steel (No. 1.4988). The O.D. of cladding was 10.0 mm with a wall thickness of 0.55 mm. Besides the thermocouples on the cladding, the specimen possessed a central thermocouple. The rod power was some 1100 W/cm, the outer cladding temperature 5000C, and the burnup only some 0.2 percent. Three pins melted near the central thermocouple by a peritectic reaction between thermocouples, cladding, and fuel. Results of non-destructive and destructive post irradiation examinations are represented. (auth)
Primary Subject
Source
nd; 173 p; Translation of KFK--1919 Work performed under United States--Euratom Fast Reactor Exchange Program.
Record Type
Report
Report Number
Country of publication
ACTINIDE COMPOUNDS, ALLOYS, BREEDER REACTORS, CARBIDES, CARBON ADDITIONS, CARBON COMPOUNDS, CHROMIUM ALLOYS, CORROSION RESISTANT ALLOYS, DISTRIBUTION, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, IRON ALLOYS, IRON BASE ALLOYS, LIQUID METAL COOLED REACTORS, PLUTONIUM COMPOUNDS, RADIATION EFFECTS, REACTOR COMPONENTS, REACTORS, STEELS, TRANSITION ELEMENT ALLOYS, TRANSURANIUM COMPOUNDS, URANIUM COMPOUNDS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Weimar, P.; Sebening, H.
Kernforschungszentrum Karlsruhe (F.R. Germany)
Kernforschungszentrum Karlsruhe (F.R. Germany)
AbstractAbstract
[en] Included are data on the fuel pin design, specifications, and fabrication as well as a detailed description of irradiation and post irradiation examination results
Original Title
LMFBR
Primary Subject
Source
nd; 116 p; Translation of KFK--2106 Work performed under United States--Euratom Fast Reactor Exchange Program.
Record Type
Report
Report Number
Country of publication
ACTINIDE COMPOUNDS, BREEDER REACTORS, CHALCOGENIDES, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, FUEL ELEMENTS, IRRADIATION REACTORS, LIQUID METAL COOLED REACTORS, MATERIALS TESTING REACTORS, OXIDES, OXYGEN COMPOUNDS, PLUTONIUM COMPOUNDS, PLUTONIUM OXIDES, RADIATION EFFECTS, REACTOR COMPONENTS, REACTORS, TANK TYPE REACTORS, TESTING, THERMAL REACTORS, TRANSURANIUM COMPOUNDS, URANIUM COMPOUNDS, URANIUM OXIDES, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Weimar, P.; Fiedler, H.
Kernforschungszentrum Karlsruhe (F.R. Germany). Inst. fuer Material- und Festkoerperforschung; Kernforschungszentrum Karlsruhe (F.R. Germany). Projekt Schneller Brueter1974
Kernforschungszentrum Karlsruhe (F.R. Germany). Inst. fuer Material- und Festkoerperforschung; Kernforschungszentrum Karlsruhe (F.R. Germany). Projekt Schneller Brueter1974
AbstractAbstract
No abstract available
Original Title
Auslegung, Bestrahlung und Nachuntersuchung des Mischkarbid-Kurzzeit-Bestrahlungsexperimentes Loop-Versuchsgruppe 4a
Primary Subject
Secondary Subject
Source
Jul 1974; 75 p; 36 figs.; 12 tabs.; 20 refs.; with 2 apps.
Record Type
Report
Report Number
Country of publication
ARGON, BONDING, BURNUP, DESTRUCTIVE TESTING, EXPERIMENTAL CHANNELS, FUEL PINS, HEAT TRANSFER, HELIUM, IN PILE LOOPS, IRRADIATION, ISOTOPE RATIO, MICROSTRUCTURE, MIXTURES, NEUTRON BEAMS, NONDESTRUCTIVE TESTING, PHYSICAL RADIATION EFFECTS, PLUTONIUM CARBIDES, POWER, QUALITY CONTROL, REACTOR EXPERIMENTAL FACILITIE, S CODES, SAMPLE PREPARATION, SPECIFICATIONS, STEEL-DIN-1-4988, TEMPERATURE DEPENDENCE, THERMAL ANALYSIS, THERMOCOUPLES, TIME DEPENDENCE, URANIUM CARBIDES
ACTINIDE COMPOUNDS, ALLOYS, BEAMS, CARBIDES, CARBON ADDITIONS, CARBON COMPOUNDS, CHROMIUM ALLOYS, CHROMIUM STEELS, CHROMIUM-NICKEL STEELS, COMPUTER CODES, CONTROL, CRYSTAL STRUCTURE, DISPERSIONS, ELEMENTS, ENERGY TRANSFER, FABRICATION, FUEL ELEMENTS, IRON ALLOYS, IRON BASE ALLOYS, JOINING, MATERIALS TESTING, MEASURING INSTRUMENTS, NICKEL ALLOYS, NONMETALS, NUCLEON BEAMS, PARTICLE BEAMS, PLUTONIUM COMPOUNDS, RADIATION EFFECTS, RARE GASES, REACTOR CHANNELS, REACTOR COMPONENTS, STEELS, TESTING, TRANSURANIUM COMPOUNDS, URANIUM COMPOUNDS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Weimar, P.; Sebening, H.
Kernforschungszentrum Karlsruhe (F.R. Germany). Inst. fuer Material- und Festkoerperforschung; Kernforschungszentrum Karlsruhe (F.R. Germany). Projekt Schneller Brueter1975
Kernforschungszentrum Karlsruhe (F.R. Germany). Inst. fuer Material- und Festkoerperforschung; Kernforschungszentrum Karlsruhe (F.R. Germany). Projekt Schneller Brueter1975
AbstractAbstract
No abstract available
Original Title
Auslegung, Bestrahlung und Nachuntersuchung des UO2/PuO2-Brennstab-Bestrahlungsexperimentes Mol 8-B
Primary Subject
Source
Jan 1975; 69 p; 22 figs.; 15 tabs.; 12 refs. With app.
Record Type
Report
Report Number
Country of publication
BR-2 REACTOR, DATA, DESTRUCTIVE TESTING, DIAGRAMS, FABRICATION, FBR TYPE REACTORS, FISSION PRODUCTS, FUEL CANS, FUEL PELLETS, FUEL PINS, GASES, IRRADIATION CAPSULES, IRRADIATION DEVICES, IRRADIATION PLANTS, IRRADIATION PROCEDURES, MICROSTRUCTURE, NONDESTRUCTIVE TESTING, PERFORMANCE TESTING, PLANNING, SPECIFICATIONS, TABLES
BREEDER REACTORS, CRYSTAL STRUCTURE, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, FAST REACTORS, FLUIDS, FUEL ELEMENTS, INFORMATION, IRRADIATION REACTORS, ISOTOPES, MATERIALS TESTING, MATERIALS TESTING REACTORS, RADIOACTIVE MATERIALS, REACTOR COMPONENTS, REACTORS, TANK TYPE REACTORS, TESTING, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Weimar, P.; Zimmermann, H.
Kernforschungszentrum Karlsruhe (F.R. Germany). Inst. fuer Material- und Festkoerperforschung
Kernforschungszentrum Karlsruhe (F.R. Germany). Inst. fuer Material- und Festkoerperforschung
AbstractAbstract
No abstract available
Original Title
UO2 cermets with Cr, V, or Mo
Primary Subject
Source
nd; 48 p; Translation of KFK--1839 .
Record Type
Report
Report Number
Country of publication
ACTINIDE COMPOUNDS, ALLOYS, BEAMS, CHALCOGENIDES, COBALT ALLOYS, COMPOSITE MATERIALS, HASTELLOYS, HEAT RESISTING ALLOYS, INCONEL ALLOYS, IRON ALLOYS, NICKEL ALLOYS, NICKEL BASE ALLOYS, NIOBIUM ALLOYS, NUCLEON BEAMS, OXIDES, OXYGEN COMPOUNDS, PARTICLE BEAMS, RADIATION EFFECTS, TANTALUM ALLOYS, TUNGSTEN ALLOYS, URANIUM COMPOUNDS, URANIUM OXIDES
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
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