Defect and void evolution in oxide dispersion strengthened ferritic steels under 3.2 MeV Fe+ ion irradiation with simultaneous helium injection

Kim, I.-S; Hunn, J.D; Hashimoto, Naoyuki; Larson, D.L.; Maziasz, P.J.; Miyahara, Kazuya; Lee, E.H

doi:10.1016/s0022-3115(00)00066-0

Cited by 148 publications

(68 citation statements)

References 17 publications

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“…6 In case of edge dislocation: Aϭ (1Ϫn Ϫn sin 2 f/(1Ϫn)) · cosf, Bϭ0. 7 Also f in this equation is the critical angle at which the dislocation detaches from particles, fϭ46 degrees in case of screw dislocation and fϭ19 degrees in case of edge dislocation. 16) D is the harmonic mean of l, rs, and to be calculated from Dϭ2ab/(aϩb) equation.…”

Section: ϫ3mentioning

confidence: 99%

“…It has been reported by a number of researchers [1][2][3][4][5][6][7][8][9] that MA ODS alloys possess excellent creep strength at high temperatures and high resistance to swelling in radioactive radiation. Oxide dispersion strengthened (ODS) ferritic alloys produced by mechanical alloying (MA) have been found to be effective for increasing high-temperature strength.…”

Section: Introductionmentioning

confidence: 99%

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Effect of Ti and W on the Mechanical Properties and Microstructure of 12% Cr Base Mechanical-alloyed Nano-sized ODS Ferritic Alloys

et al. 2003

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Section: ϫ3mentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Effect of Ti and W on the Mechanical Properties and Microstructure of 12% Cr Base Mechanical-alloyed Nano-sized ODS Ferritic Alloys

et al. 2003

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“…Since no prototype fusion reactors currently exist, it is difficult to directly evaluate the high-energy neutron damage environment expected to prevail in the first wall of a fusion reactor. One technique commonly used to study the evolution of defect structures and the nucleation and growth of voids utilizes transmission electron microscopy (TEM) examinations of specimens simultaneously bombarded by heavy ions and helium and/or deuterium ions through so called "dual-beam" and "triple-beam" simulation experiments [6,7]. The heavy ions create atomic displacements while the gas ions simulate the effects of transmutation gases, helium (10 appm/dpa) and hydrogen (40 appm/dpa).…”

Section: Introductionmentioning

confidence: 99%

HRTEM study of oxide nanoparticles in K3-ODS ferritic steel developed for radiation tolerance

Hsiung

Fluss

Tumey

et al. 2011

Journal of Nuclear Materials

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Crystal and interfacial structures of oxide nanoparticles and radiation damage in 16Cr-4.5Al-0.3Ti-2W-0.37 Y 2 O 3 ODS ferritic steel have been examined using high-resolution transmission electron microscopy (HRTEM) techniques. Oxide nanoparticles with a complex-oxide core and an amorphous shell were frequently observed. The crystal structure of complex-oxide core is identified to be mainly monoclinic Y 4 Al 2 O 9 (YAM) oxide compound. Orientation relationships between the oxide and the matrix are found to be dependent on the particle size. Large particles (> 20 nm) tend to be incoherent and have a spherical shape, whereas small particles (< 10 nm) tend to be coherent or semi-coherent and have a faceted interface. The observations of partially amorphous nanoparticles and multiple crystalline domains formed within a nanoparticle lead us to propose a three-stage mechanism to rationalize the formation of oxide nanoparticles containing core/shell structures in as-fabricated ODS steels. Effects of nanoparticle size and density on cavity formation induced by (Fe 8+ + He + ) dual-beam irradiation are briefly addressed.

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“…These alloys have indeed demonstrated outstanding high temperature properties and remarkable tolerance to irradiation-induced displacement damage [45,[49][50][51].…”

Section: Stable Microstructuresmentioning

confidence: 99%

Atomic-scale design of radiation-tolerant nanocomposites

2010

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Recent work indicates that materials with nanoscale architectures, such as nanolayered Cu-Nb composites and nanoscale oxide dispersion-strengthened steels, are both thermally stable and offer improved performance under irradiation.Current understanding of the atomic-level response of such materials to radiation yields insights into how controlling composition, morphology and interface-defect interactions may further enable atomic-scale design of radiation tolerant nanostructured composite materials. With greater understanding of irradiationassisted degradation mechanisms, this bottom-up design approach may pave the way for creating the extreme environment-tolerant structural materials needed to meet the world's clean energy demand by expanding use of advanced fission and future fusion power.2

show abstract

Defect and void evolution in oxide dispersion strengthened ferritic steels under 3.2 MeV Fe+ ion irradiation with simultaneous helium injection

Cited by 148 publications

References 17 publications

Effect of Ti and W on the Mechanical Properties and Microstructure of 12% Cr Base Mechanical-alloyed Nano-sized ODS Ferritic Alloys

Effect of Ti and W on the Mechanical Properties and Microstructure of 12% Cr Base Mechanical-alloyed Nano-sized ODS Ferritic Alloys

HRTEM study of oxide nanoparticles in K3-ODS ferritic steel developed for radiation tolerance

Atomic-scale design of radiation-tolerant nanocomposites

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