Creep and damage anisotropies of 9%Cr and 14 %Cr ODS steel cladding - Archive ouverte HAL Access content directly
Journal Articles Journal of Nuclear Materials Year : 2018

Creep and damage anisotropies of 9%Cr and 14 %Cr ODS steel cladding

(1) , (1) , (1) , (2)
1
2

Abstract

Two Oxide Dispersion Strengthened (ODS) steel tubes, obtained by means of hot extrusion and cold rolling, are studied as potential materials for cladding applications in sodium-cooled fast reactors. A 9percentCr martensitic tube (Fe-9Cr-1W-0.3Ti-0.25Y$_2$O$_3$) with isotropic microstructure is compared to a 14%Cr ferritic tube (Fe-14Cr-1W-0.3Ti-0.25Y$_2$O$_3$) with elongated grains and a strong texture. Tile and notched ring specimens are used to perform uniaxial creep tests at 650°C in the longitudinal and transverse directions of the tubes. The 14%Cr ODS steel tube exhibits strong mechanical anisotropies, while the 9%Cr presents only a slight anisotropy in creep resistance, presumably due to the influence of specimen geometry on mechanical fields. Both intergranular and ductile zones have been observed on the fracture surfaces of the uniaxial creep specimens, suggesting the competition of two damage mechanisms. Damage for both tubes appeared anisotropic, with orientated cracks in the rolling directions on the ring specimens and the 14%Cr tile specimens. Internal pressure creep tests also performed at 650DC show complementary results for both tubes in agreement with ring specimens- ones, validating their use for hoop properties assessment. Overall, while the 14%tCr ODS steel tube is strong in the longitudinal direction, the 9%Cr tube proves as resistant in the transverse direction.
Fichier principal
Vignette du fichier
201800002824.pdf (1.93 Mo) Télécharger le fichier
Origin : Files produced by the author(s)
Loading...

Dates and versions

cea-02339434 , version 1 (20-11-2019)

Identifiers

  • HAL Id : cea-02339434 , version 1

Cite

T. Jaumier, L. Vincent, S. Vincent, R. Desmorat. Creep and damage anisotropies of 9%Cr and 14 %Cr ODS steel cladding. Journal of Nuclear Materials, 2018, 518, pp.274-286. ⟨cea-02339434⟩
32 View
102 Download

Share

Gmail Facebook Twitter LinkedIn More