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Schirra, M.; Falkenstein, A.; Huebner, R.; Materna-Morris, E.; Bennek-Kammerichs, B.; Ehrlich, K.
Nuclear safety research project (PSF). 1999 annual report2000
Nuclear safety research project (PSF). 1999 annual report2000
AbstractAbstract
[en] 'Structural integrity' comprises several research activities: The examination of creep and creep rupture behaviour of the austenitic steel 316 L(N)-DIN 1.4919 on low stress levels at 550 and 600 C; investigations on swelling, irradiation creep and related microstructural changes in several austenitic alloys under high-fluence irradiations (PFR-experiment) and the fracture analysis of ferritic and austenitic reactor steels under variable deformation rates and for different sample geometries are further topics of experimental investigations. (orig.)
[de]
In diesem Vortrag sind mehrere Aktivitaeten des IMF I zusammengefasst. Untersuchungen zum Kriech- und Zeitstandfestigkeitsverhalten werden am Werkstoff 316 L(N)-DIN 1.4919 bei 550 und 600 C im anwendungsrelevanten Spannungsbereich unterhalb der 0,2%-Streckgrenze durchgefuehrt. Im Bestrahlungsprojekt PFR-M2 sind Untersuchungen zum Schwell- und Kriechverhalten und zur mikrostrukturellen Entwicklung unter Bestrahlung an verschiedenen Staehlen abgeschlossen und dokumentiert worden. Das Bruchverhalten zweier LWR-Reaktorstaehle wird fuer unterschiedliche Probengeometrien und stark variierende Verformungsgeschwindigkeiten studiert. (orig.)Original Title
Untersuchungen an Strukturmaterialien der Kerntechnik
Primary Subject
Source
Muehl, B. (ed.); Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Projekt Nukleare Sicherheitsforschung; 707 p; ISSN 0947-8620;
; Aug 2000; p. 541-554; Available from TIB Hannover: ZA 5141(6480); 1 refs.

Record Type
Miscellaneous
Report Number
Country of publication
CREEP, FAST NEUTRONS, FERRITIC STEELS, FRACTOGRAPHY, FRACTURE PROPERTIES, GRAIN SIZE, MICROSTRUCTURE, NEUTRON FLUENCE, RADIATION EFFECTS, REACTOR COMPONENTS, REACTOR MATERIALS, REACTOR SAFETY, STAINLESS STEEL-316L, STRAIN RATE, SWELLING, TEMPERATURE DEPENDENCE, TEMPERATURE RANGE 0400-1000 K, TENSILE PROPERTIES
ALLOYS, AUSTENITIC STEELS, BARYONS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM STEELS, CHROMIUM-MOLYBDENUM STEELS, CHROMIUM-NICKEL STEELS, CHROMIUM-NICKEL-MOLYBDENUM STEELS, CORROSION RESISTANT ALLOYS, DEFORMATION, ELEMENTARY PARTICLES, FERMIONS, HADRONS, HEAT RESISTANT MATERIALS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, LOW CARBON-HIGH ALLOY STEELS, MATERIALS, MECHANICAL PROPERTIES, MICROSTRUCTURE, MOLYBDENUM ALLOYS, NEUTRONS, NICKEL ALLOYS, NUCLEONS, SAFETY, SIZE, STAINLESS STEELS, STEEL-CR17NI12MO3-L, STEELS, TEMPERATURE RANGE, TRANSITION ELEMENT ALLOYS
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