Irradiation creep and microstructural changes in an advanced ODS ferritic steel during helium implantation under stress

Chen, Jiachao; Pouchon, Manuel A.; Kimura, Akihiko; Jung, P.; Hoffelner, Wolfgang

doi:10.1016/j.jnucmat.2008.12.081

Cited by 37 publications

(20 citation statements)

References 13 publications

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“…This compliance compared very well with the average compliance found for different ferritic ODS steels (including PM2000), [19] which was determined to be 8.9AE10 À6 /(MPaAEd _ pa). From these findings, it can be assumed that the TiAl alloys behave in a manner similar to ferritic materials, which would make them superior to austenitic materials with respect to irradiation behavior (e.g., Reference 20).…”

Section: B Irradiation Creepsupporting

confidence: 72%

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Thermal and Irradiation Creep Behavior of a Titanium Aluminide in Advanced Nuclear Plant Environments

Magnusson

Chen

Hoffelner

2009

Metall Mater Trans A

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Titanium aluminides are well-accepted elevated temperature materials. In conventional applications, their poor oxidation resistance limits the maximum operating temperature. Advanced reactors operate in nonoxidizing environments. This could enlarge the applicability of these materials to higher temperatures. The behavior of a cast gamma-alpha-2 TiAl was investigated under thermal and irradiation conditions. Irradiation creep was studied in beam using helium implantation. Dog-bone samples of dimensions 10 9 2 9 0.2 mm 3 were investigated in a temperature range of 300°C to 500°C under irradiation, and significant creep strains were detected. At temperatures above 500°C, thermal creep becomes the predominant mechanism. Thermal creep was investigated at temperatures up to 900°C without irradiation with samples of the same geometry. The results are compared with other materials considered for advanced fission applications. These are a ferritic oxide-dispersion-strengthened material (PM2000) and the nickel-base superalloy IN617. A better thermal creep behavior than IN617 was found in the entire temperature range. Up to 900°C, the expected 10 4 hour stress rupture properties exceeded even those of the ODS alloy. The irradiation creep performance of the titanium aluminide was comparable with the ODS steels. For IN617, no irradiation creep experiments were performed due to the expected low irradiation resistance (swelling, helium embrittlement) of nickel-base alloys.

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Section: B Irradiation Creepsupporting

confidence: 72%

“…This material was developed at Plansee (Austria) for high-temperature applications. It consists of a ferritic matrix containing about 19 Article published online September 11, 2009 creep comparison, because the irradiation properties are better for ferritic alloys than for austenites and nickel is very prone to helium embrittlement.…”

Section: Introductionmentioning

confidence: 99%

Thermal and Irradiation Creep Behavior of a Titanium Aluminide in Advanced Nuclear Plant Environments

Magnusson

Chen

Hoffelner

2009

Metall Mater Trans A

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“…Dissolution of Y2O3 during mechanical alloying (MA) and precipitation of Y2O3-rich nano-scale clusters/precipitates during hot isostatic pressing/hot extrusion play key roles in producing nano-structured ODS steels. So preparing ODS alloys by adding Y2O3 to RAFM to improve its high-temperature creep resistance and radiation-induced swelling resistance has become an important research area [5][6][7].…”

Section: The Methods Of Preparing Ods Rafm Steelsmentioning

confidence: 99%

Development in Preparing Methods of the Nano-Structured ODS RAFM Steels

Qiao¹,

Li²,

Yin³

2017

dtetr

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Abstract. The Mechanical alloying method, the sol-gel-spark plasma sintering method and the vacuum casting method are researched which are used to prepare nano-structured oxide dispersion strengthened (ODS) RAFM steels. Nano-structured ODS RAFM steels can be obtained by The Mechanical alloying methods and the sol-gel-spark plasma sintering methods. Micron-structured ODS RAFM steels can be obtained by vacuum casting method. The microstructure of the material manufactured by different methods are compared.

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“…Mechanisms for irradiation creep are rather dependent on the nature of irradiation-induced defects then on conventional hardening mechanisms. A more detailed study of irradiation creep of these materials is given in [14].…”

Section: Irradiation Creep and Thin Strip Samplesmentioning

confidence: 99%

Characterization of Irradiation Damage of Ferritic ODS Alloys with Advanced Micro-Sample Methods

et al. 2008

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Oxide dispersion strengthened (ODS) steels are candidate materials for advanced electric energy and heat generation plants (nuclear, fossil). Understanding the degradation of mechanical properties of these alloys as a result of service exposure is necessary for safe design. For advanced nuclear applications combinations of temperature, irradiation and stress are important damage conditions. They are studied either with neutron irradiated samples (often highly active) or with ion-irradiated samples (irradiation damage often limited to only a few micrometer deep areas). High activity of samples and limited sample volume claim to subsized samples like nano-indentation, micro-pillar compression or thin strip creep testing. Irradiation hardening and irradiation creep were studied with these methods. Ferritic ODS steels with 19% chromium were investigated. The materials were studied in qualities differing in grain sizes and in sizes of the dispersoids. Irradiation was performed in an accelerator using He-ions. Irradiation damage profiles could be well analyzed with indentation. Yield stress determined with compression tests of single-crystal micropillars was well comparable with tension tests performed along the same crystallographic orientation. Irradiation creep of samples with different sizes of dispersoids revealed only a small influence of particle size being is in contrast with thermal creep but consistent with expectations from other investigations.

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Irradiation creep and microstructural changes in an advanced ODS ferritic steel during helium implantation under stress

Cited by 37 publications

References 13 publications

Thermal and Irradiation Creep Behavior of a Titanium Aluminide in Advanced Nuclear Plant Environments

Thermal and Irradiation Creep Behavior of a Titanium Aluminide in Advanced Nuclear Plant Environments

Development in Preparing Methods of the Nano-Structured ODS RAFM Steels

Characterization of Irradiation Damage of Ferritic ODS Alloys with Advanced Micro-Sample Methods

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