Radiation resistance and thermal creep of ODS ferritic steels

Сагарадзе, В. В.; Шалаев, В. И.; Арбузов, В. Л.; Goshchitskii, B. N.; Tian, Yuan; Wan, Qun; Jiguang, Sun

doi:10.1016/s0022-3115(01)00511-6

Cited by 79 publications

(36 citation statements)

References 4 publications

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“…This is assumed to be either linear in T or linear in 1/T. [25], ferritic ODS Japan, 1, 9% Cr ODS Japan replotted from [26,88], IN617 replotted from [27], TiAl replotted from [15,16], grade 91 replotted from [18], PM2000 bar parameterized according to Eq. 2 replotted from [28], grade 91TMT replotted from [12].…”

Section: Stress Rupture and Creepmentioning

confidence: 99%

Damage assessment in structural metallic materials for advanced nuclear plants

Hoffelner

2010

J Mater Sci

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Future advanced nuclear plants are considered to operate as cogeneration plants for electricity and heat. Metals and alloys will be the main portion of structural materials employed (including fuel claddings). Due to the operating conditions these materials are exposed to damaging conditions like creep, fatigue, irradiation and its combinations. The paper uses the most important alloys: ferritic-martensitic steels, superalloys, oxide dispersion strengthened steels and to some extent titanium aluminides to discuss its responses to these exposure conditions. Extrapolation of stress rupture data, creep strain, swelling, irradiation creep and creep-fatigue interactions are considered. Although the stress rupture-and the creep behavior seem to meet expectations, the long design lives of 60 years are really challenging for extrapolations and particularly questions like negligible creep or occurrence of diffusion creep need special attention. Ferritic matrices (including oxide dispersion strengthened (ODS), steels) have better irradiation swelling behavior than austenites. Presence and size of dispersoids having a strong influence on high-temperature strength bring only insignificant improvements in irradiation creep. A strain-range-separation based approach for creep-fatigue interactions is presented which allows a real prediction of creep-fatigue lives. An assessment of capabilities and limitations of advanced materials modeling tools with respect to damage development is given.

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Section: Stress Rupture and Creepmentioning

confidence: 99%

Damage assessment in structural metallic materials for advanced nuclear plants

Hoffelner

2010

J Mater Sci

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“…28 Most recently, a European effort is intended to produce large experimental batches of material based on the basic steel EUROFER 97 (~Fe-8.9Cr-1.1W-0.2V-0.14Ta-0.42Mn-0.11C) gas atomized, with Y 2 O 3 added (at levels of 0.3 and 0.5 wt%), mechanically alloyed and then HIPed, 35 and various laboratories around the world are recommending other novel compositions for fusion ODS alloys. 36,37 Effects of Irradiation A limited number of irradiation experiments have been performed on ODS ferritic steels. These include microstructure and swelling, tensile deformation, charpy impact, biaxial creep, and stress rupture to neutron doses as high as 200 dpa.…”

Section: Stress Psimentioning

confidence: 99%

Novel Concepts for Damage-Resistant Alloys in Next Generation Nuclear Power Systems

Bruemmer¹,

Andersen²,

Was³

2002

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“…Among various oxides, Y 2 O 3 NPs are typically added into the ODS steels to improve their performances at high temperature, severe irradiation and corrosion environments in the fission and fusion power plants [10][11][12].…”

Section: Introductionmentioning

confidence: 99%