Published September 1994
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Effect of fabrication and test parameters on the fracture toughness of aged cast duplex stainless steels
Description
Cast duplex stainless steels used in the primary circuit elbows of pressurized water reactors undergo thermal aging at their service temperature, around 300 deg C. This affects their toughness. In order to assess the residual toughness of elbows, two methods are applicable : an indirect one based on chemical composition and a direct one, newly developed, based on the testing of mini-CT specimens taken from elbows. The indirect method can be over conservative. The direct method has proved feasible provided several parameters are taken into account. It was shown that a correct assessment of toughness requires a large number of specimens, and a special care in the choice of sampling areas. (authors). 5 refs., 7 figs., 2 tabs., 1 appendix
Availability note (English)
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27048127.pdf
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Additional details
Additional titles
- Original title (French)
- Effet de parametres de fabrication et d'essai sur la tenacite des aciers inoxydables austeno-ferritiques vieillis
Publishing Information
- Imprint Pagination
- 12 p.
- Report number
- EDF--95-NB-00059
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 27048127
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CAST IRON; CHARPY TEST; CRACK PROPAGATION; GRAIN DENSITY; PIPES; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; STAINLESS STEELS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; COOLING SYSTEMS; CRYSTAL STRUCTURE; DESTRUCTIVE TESTING; ENRICHED URANIUM REACTORS; HIGH ALLOY STEELS; IMPACT TESTS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS TESTING; MECHANICAL TESTS; MICROSTRUCTURE; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SILICON ALLOYS; STEELS; TESTING; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS