2010
DOI: 10.1007/s12666-010-0033-x
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Creep-fatigue crack behaviour of a mod. 9Cr-1Mo steel structure with weldments

Abstract: An assessment of a creep-fatigue crack initiation and growth for a Mod. 9Cr-1Mo steel structure with weldments has been carried out based on an extended French RCC-MR A16 procedure. The A16 defect assessment guide provides assessment procedures for a creep-fatigue crack initiation and growth for an austenitic stainless steel, but no guidelines are available yet for a Mod. 9Cr-1Mo steel. A creep-fatigue structural test was carried out for a Mod. 9Cr-1Mo specimen with two hours of a hold time at 873 K and variou… Show more

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Cited by 12 publications
(6 citation statements)
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“…In this context behaviour of the surrogate material with the potential coolant is an important issue to be discussed before selection and development of material for this specific structural application. Fe9Cr1Mo steels or P91 is a structure materials presently used in the nuclear fission reactors worldwide [7,8] because of its unique physical properties such as high tensile strength, high hardness, fatigue resistance and resistance to irradiation. It appears promising candidate surrogate material for the development of fusion reactor first wall structure component with a suitable modification in the composition to stand against high neutron flux (neutron flux in fusion reactor will be substantially higher compared to usual nuclear reactor based on fission reaction) [9][10][11] and compatible with the proposed coolant.…”
Section: Introductionmentioning
confidence: 99%
“…In this context behaviour of the surrogate material with the potential coolant is an important issue to be discussed before selection and development of material for this specific structural application. Fe9Cr1Mo steels or P91 is a structure materials presently used in the nuclear fission reactors worldwide [7,8] because of its unique physical properties such as high tensile strength, high hardness, fatigue resistance and resistance to irradiation. It appears promising candidate surrogate material for the development of fusion reactor first wall structure component with a suitable modification in the composition to stand against high neutron flux (neutron flux in fusion reactor will be substantially higher compared to usual nuclear reactor based on fission reaction) [9][10][11] and compatible with the proposed coolant.…”
Section: Introductionmentioning
confidence: 99%
“…The amount of a CCG during the given hold time t mi is calculated from Eqs. (15) and (16). It should be noted that the formula for the 2002 edition shown in Eq.…”
Section: Calculation Of the Ccg (δA C )mentioning
confidence: 99%
“…Research on developing the assessment procedures on creepfatigue crack behavior for Mod.9Cr-1Mo steel are underway [13][14][15][16][17].…”
Section: Introductionmentioning
confidence: 99%
“…Fine cracks can appear on steel structures under the long-term load effect [1][2], thus cracks can gradually extend over time without examination and maintenance till the whole component completely fractures. With the development of technology, the application of metal materials to engineering is irreplaceable; however, it also brings disastrous accidents.…”
Section: Introductionmentioning
confidence: 99%