Published 1976
| Version v1
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Status of development of cladding and structural materials for the SNR core elements
Creators
- 1. Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch Gladbach (Germany, F.R.)
Description
Problems concerning high-temperature plasticity and the swelling of cladding and fuel channel materials of the SNR-300 are dealt with. Plasticity of the material 1.4970 under short-term and long-term stress (104h), the 0.2% yield point, and elongation before reduction of area of the irradiated material as well as creep rupture strength and the 0.2% creep limit of pipes made of 1.4970 (t = 7000C, irradiated and non-irradiated) are presented in diagrammes. Creep induced by irradiation of the materials 1.4970 and 1.4981 is also dealt with. (HR)
Abstract (German)
Es werden Fragen der Hochtemperaturplastizitaet und des Schwellens von Werkstoffen fuer das Huellrohr und den Brennelementkasten des SNR-300 behandelt. Die Plastizitaet des Werkstoffes 1.4970 bei Kurz- und Langzeitbelastung (104h), die 0,2% Streckgrenze und die Gleichmassdehnung des bestrahlten Werkstoffes sowie die Zeitstandfestigkeit und die 0,2% Zeitdehngrenze von Rohren aus 1.4970 (T = 7000C, bestrahlt und unbestrahlt) sind in Diagrammen dargestellt. Weiterhin wird auf das bestrahlungsinduzierte Kriechen der Werkstoffe 1.4970 und 1.4981 eingegangen. (HR)
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Additional details
Additional titles
- Original title (German)
- Entwicklungsstand des Huell- und Strukturmaterials fuer SNR-Kernelemente
Publishing Information
- Imprint Title
- The fuel element of the LMFBR
- Journal Page Range
- p. 80-88.
- Report number
- KFK--2416
Conference
- Title
- KTG technical day on fuel element of the sodium-cooled breeder.
- Dates
- 28 - 29 Oct 1976.
- Place
- Karlsruhe, Germany, F.R.
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 8335295
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BRITTLENESS; CREEP; FUEL CANS; FUEL CHANNELS; HIGH TEMPERATURE; IRRADIATION; PLASTICITY; SNR REACTOR; STEEL-DIN-1-4970; STEEL-DIN-1-4981; STRESSES; SWELLING; YIELD STRENGTH
- Descriptors DEC
- ALLOYS; BREEDER REACTORS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-NICKEL STEELS; DEFORMATION; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; HEAT RESISTING ALLOYS; IRON ALLOYS; IRON BASE ALLOYS; LIQUID METAL COOLED REACTORS; MECHANICAL PROPERTIES; NICKEL ALLOYS; NIOBIUM ADDITIONS; POWER REACTORS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; SODIUM COOLED REACTORS; STEELS; TANTALUM ADDITIONS; TITANIUM ADDITIONS; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 8 figs.; 3 tabs.; 10 refs. Imprint:Das Brennelement des Natriumbrueters.
- Secondary number(s)
- AED-Conf--76-735-012.