Effect of irradiation on creep-fatigue interaction of DIN 1.4948 stainless steel plate and welds at 823 K
Description
The effect of irradiation on creep-fatigue interaction has been studied for DIN 1.4948 plate material and welded joints tested at 823 K. Creep exposure lasted up to 4100 h prior to low cycle fatigue testing, which was carried out at a total strain range of 0.6% and a strain rate of 3x10-3s-1 at 823 K. Unirradiated plate shows a total damage factor, D, of about 1.0, unirradiated welded joints show a total damage factor of about 0.85. Irradiated plate and welded joints give total damage factors below 0.5, using reference times-to-rupture. The reduction by irradiation is caused by the easy creep crack development resulting from helium embrittlement early in creep life. When using the time-to-rupture for plate material in irradiated condition for the total damage factor calculation the bilinear ASME approach forms a lower boundary for our experimental results. Welded joints neither in reference nor in irradiated condition satisfy the linear or the bilinear approach. The experimentally determined total damage factors of welded remain below the ASME proposed even when taking the time-to-rupture in irradiated condition for the calculations. The accelerated creep crack growth in the heat affected zone near the root weld pass gives the main contribution to the reduction of D-value by irradiation. (author)
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Additional details
Publishing Information
- Imprint Title
- Specialists meeting on properties of primary circuit structural materials including environmental effects
- Imprint Pagination
- 122 p.
- Journal Page Range
- p. 218-225
- Report number
- IWGFR--22
Conference
- Title
- IAEA-IWGFR specialists meeting on properties of primary circuit structural materials including environmental effects
- Dates
- 17-21 Oct 1977
- Place
- Bergisch Gladbach (Germany)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 32019350
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGING; CREEP; DAMAGE; PHYSICAL RADIATION EFFECTS; REACTOR COMPONENTS; REACTOR MATERIALS; RUPTURES; SODIUM; SODIUM COOLED REACTORS; STEEL-X6CRNI1811; TEMPERATURE RANGE 0400-1000 K
- Descriptors DEC
- ALKALI METALS; ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CORROSION RESISTANT ALLOYS; ELEMENTS; FAILURES; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LIQUID METAL COOLED REACTORS; MATERIALS; MECHANICAL PROPERTIES; METALS; NICKEL ALLOYS; RADIATION EFFECTS; REACTORS; STAINLESS STEELS; STEEL-CR18NI11; STEELS; TEMPERATURE RANGE; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 3 refs, 11 figs, 2 tabs