Helium effects on creep properties of Fe–14CrWTi ODS steel at 650 °C

Chen, Jie; Jung, P.; Rebac, Tomislav; Duval, F.; Sauvage, Thierry; Carlan, Y. de; Barthe, M.F.

doi:10.1016/j.jnucmat.2014.07.010

Cited by 19 publications

(6 citation statements)

References 34 publications

(50 reference statements)

Supporting

Mentioning

Contrasting

Order By: Relevance

“…It is interesting that some of the voids observed after irradiation at 625 C appear be attached to the interface of dispersoid and matrix, and formed inside of the dispersoids. The observation is consistent with the previous studies, which shows the trapping of bubbles by the dispersoid/matrix interface at elevated temperatures [15,16,18].…”

Section: Resultssupporting

confidence: 93%

“…Among F/M alloys, oxidedispersion-strengthened (ODS) variants are also attractive for nuclear applications due to their strong contribution to creep resistance, especially at higher temperatures where ferritic alloys are much weaker than austenitic alloys [5,14,15]. The dispersoids pin and stabilize the grain boundaries against recrystallization and grain growth and may act as sinks for both point defects and transmutant helium atoms [13e18].…”

Section: Introductionmentioning

confidence: 99%

“…Trapping of defects and helium at the dispersoid/matrix interface was evidenced by comparing irradiation-induced microstructure changes of ODS and non-ODS alloys [18]. Such a trapping effect was believed to suppress helium bubble growth and enhance the resistance against helium embrittlement of the material [15,16,18]. Ukai et al have developed a series of ODS alloys combining mesoscopic optimization of dual phase ferrite/tempered martensite with nano-scale optimization of ultra-fine oxide particles to strongly enhance high temperature creep resistance and void swelling resistance [19e22].…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Temperature dependent dispersoid stability in ion-irradiated ferritic-martensitic dual-phase oxide-dispersion-strengthened alloy: Coherent interfaces vs. incoherent interfaces

et al. 2016

View full text Add to dashboard Cite

a b s t r a c tIn this study, the microstructure of a 12Cr ferritic-martensitic oxide-dispersion-strengthened (ODS) alloy is studied before and after Fe ion irradiation up to 200 peak displacements per atom (dpa). Irradiation temperature ranges from 325 to 625 C. Before irradiation, both coherent and incoherent dispersoids exist in the matrix. In response to irradiation, the mean sizes of dispersoids in both the ferrite and tempered martensite phases change to equilibrium values that increase with irradiation temperature. The evolution of dispersoids under irradiation is explained by a competition between athermalradiation-driven shrinkage and thermal-diffusion-driven growth, with interface coherency affecting the growth mechanism. However, each coherency type exhibits different evolution behavior under irradiation. Coherent dispersoids, regardless of their initial size, change toward an equilibrium size at each temperature tested. On the other hand, incoherent dispersoids are destroyed at lower test temperatures but survive while shrinking in size at higher temperatures. This difference in behavior can be explained by the lower interfacial energy of coherent dispersoids in comparison with incoherent dispersoids. This study sheds light on the roles of interface configurations in maintaining dispersoid integrity under irradiation.

show abstract

Section: Resultssupporting

confidence: 93%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Temperature dependent dispersoid stability in ion-irradiated ferritic-martensitic dual-phase oxide-dispersion-strengthened alloy: Coherent interfaces vs. incoherent interfaces

et al. 2016

View full text Add to dashboard Cite

show abstract

“…The pressures inside the bubbles are very large, which can destroy the mechanical properties of the materials. [4][5][6][7][8] The changes in the mechanical properties of the materials reduce the safety of nuclear installations and shorten their service life, thus it becomes important to study the behaviors of helium atoms in metals.…”

Section: Introductionmentioning

confidence: 99%

Growth mode of helium crystal near dislocations in titanium

et al. 2018

View full text Add to dashboard Cite

The helium bubble structure and growth modes near dislocations in titanium are studied using the molecular dynamics method. A helium crystal with an HCP structure in titanium is found to have a lattice constant of 1.977 Å at 0 K. On either side of the slip plane, helium bubbles form in the (001) plane, but they are in different growth modes. On the side of the slip plane with full atomic layers, helium bubbles grow toward the slip plane and easily cross the slip plane. In the growth process, the position of the top surface of the helium bubble remains almost unchanged. On the other side of the slip plane, the helium bubble grows initially toward the dislocation core, but it is difficult to cross the slip plane, which results in growth in the opposite direction upon reaching the slip plane.

show abstract

“…Earlier research revealed that various energetic ions caused defects on different materials, including micro-cracks, bubbles, blisters, pinholes, crystal damage, etc. [2][3][4][5][6] In order to examine the characteristic changes of irradiated samples, some experiments have been conducted. [7][8][9][10] Li et al 7 used a micro-compression test to study the effect of a nanometer-scale helium bubble on the strength and deformability of sputter-deposited Cu and Cu/ Nb multi-layers.…”

Section: Introductionmentioning

confidence: 99%