Oxide dispersion-strengthened/ferrite-martensite steels as core materials for Generation IV nuclear reactors

Ukai, Shigeharu; Ohtsuka, Satoshi; Kaito, Takeji; Carlan, Y. de; Ribis, J.; Malaplate, J.

doi:10.1016/b978-0-08-100906-2.00010-0

Cited by 38 publications

(31 citation statements)

References 87 publications

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“…%) ODS ferritic steel produced by powder metallurgy, starting from pre-alloyed 14Cr steel, TiH 2 and Y 2 O 3 powders to set the chemical composition. The ratio between yttrium, oxygen and titanium contents was set from a previous optimization work, in order to get a fine distribution of stable nano-precipitates at the end of the whole processing cycle [Ukai et al, 2017], [Chauhan et al, 2017], [Odette, 2018]. High energy ball-milling was followed by hot extrusion at 1150°C and by a 1-hour annealing treatment at 1050°C, leading to a 17-mm-diameter rod [JL Boutard et al, 2014].…”

Section: Methodsmentioning

confidence: 99%

“…Two chromium contents, namely, 9wt% and 14wt%, have been considered; they respectively lead to a recrystallised martensite and to a fully ferritic microstructure with higher resistance to corrosive products used in fuel disposal procedures. Their development through powder metallurgy manufacturing, their microstructure and current properties have been comprehensively reviewed recently ( [Ukai et al, 2017], [Odette, 2018]), so that only essential features are reported in the following. Their body centered cubic matrix ensures good resistance to irradiation induced swelling [A. Alamo et al, 2004].…”

Section: Introductionmentioning

confidence: 99%

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Anisotropic intergranular damage development and fracture in a 14Cr ferritic ODS steel under high-temperature tension and creep

Salmon-Legagneur

Vincent

Garnier

et al. 2018

Materials Science and Engineering: A

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This work addresses damage mechanisms at high temperature of a hot extruded 14Cr oxide dispersion strengthened steel rod, in particular, anisotropy induced by its strong morphological and crystallographic texture. Under uniaxial tension, intergranular damage and unstable fracture increased with test temperature; they appeared much easier along the rod axis than perpendicular to it. Creep fracture of smooth specimens involved crack initiation from the side surfaces and intergranular crack propagation, accompanied by intergranular damage.In order to get rid of fracture surface oxidation by the air environment, a methodology promoting crack nucleation from inside the specimen was built. From tensile and creep tests on notched specimens the fracture initiation location and fracture stability were first mapped as a function of test temperature, maximal stress triaxiality and loading direction. Then, for the first time to the authors' knowledge, interrupted tests on notched tensile and creep specimens, followed by low-temperature fracture allowed revealing fracture surfaces formed at high temperature, but unconnected to the external environment. Intergranular fracture and grain boundary grooving were evidenced there, together with strong chemical reactivity at the surface of internal cavities during damage development at high temperature.

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Section: Methodsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Anisotropic intergranular damage development and fracture in a 14Cr ferritic ODS steel under high-temperature tension and creep

Salmon-Legagneur

Vincent

Garnier

et al. 2018

Materials Science and Engineering: A

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“…The origin of this relative underperformance has not been yet clearly identified. [11,20,32,44,56,58,60]…”

Section: Comparison With Commercial or Experimental Ods Steelsmentioning

confidence: 99%

“…For alloys with chromium content below 12% Cr, there is a phase transformation above 850°C and isotropic martensitic or ferritic microstructure can be obtained after the phase transformation. For alloys with chromium content above 13% Cr, there is no phase transformation; only ferritic microstructures can be obtained [11]. Furthermore, abnormal grain growth leading to reduced mechanical properties at recrystallization temperatures (1400°C) for high chromium ferritic ODS steels makes such treatments difficult to control [1,12].…”

Section: Introductionmentioning

confidence: 99%

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

Jaumier

Vincent

et al. 2019

Journal of Nuclear Materials

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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 9%Cr martensitic tube (Fe-9Cr-1W-0.3Ti-0.25Y2O3) with isotropic microstructure is compared to a 14%Cr ferritic tube (Fe-14Cr-1W-0.3Ti-0.25Y2O3) 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 650°C show complementary results for both tubes in agreement with ring specimens' ones, validating their use for hoop properties assessment. Overall, while the 14%Cr ODS steel tube is strong in the longitudinal direction, the 9%Cr tube proves as resistant in the transverse direction.

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“…Since then, many applications have been foreseen for this type of advanced material, mostly in circumstances where a combination of creep strength and oxidation resistance is of paramount importance. For example, a new generation of Fe-Cr-Al ferritic steels is being considered as structural material for new GEN-IV fission reactors [2]. As the ferritic state makes the alloy resistant to radiation-induced swelling, and the aluminum content boosts the formation of a protective alumina layer against liquid metal embrittlement, some of the alloys of this family were intended for use in the manufacture of tubes for new-generation nuclear reactors cooled by liquid sodium at about 700 • C [3].…”

Section: Introductionmentioning

confidence: 99%

Effect of Extensive and Limited Plastic Deformation on Recrystallized Microstructure of Oxide Dispersion Strengthened Fe-Cr-Al Alloy

Capdevila

Rementería

Aranda

et al. 2018

Metals

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Ferritic oxide dispersion-strengthened alloys (ODS) are manufactured using a mechanical alloying process. The development of a coarse-grained microstructure during recrystallization has been detected and discussed by several authors, but the mechanism of grain growth remains uncertain. Recent work has emphasized the large influence of non-uniformities on the development of the recrystallized microstructure. The purpose of the present work is to study the effect of both slight heterogeneous plastic strains and strong directional deformation on recrystallization of a ferritic Fe-base ODS alloy.

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Oxide dispersion-strengthened/ferrite-martensite steels as core materials for Generation IV nuclear reactors

Cited by 38 publications

References 87 publications

Anisotropic intergranular damage development and fracture in a 14Cr ferritic ODS steel under high-temperature tension and creep

Anisotropic intergranular damage development and fracture in a 14Cr ferritic ODS steel under high-temperature tension and creep

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

Effect of Extensive and Limited Plastic Deformation on Recrystallized Microstructure of Oxide Dispersion Strengthened Fe-Cr-Al Alloy

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