Simulation of JR-curves for reactor pressure vessels steels on the basis of a ductile fracture model

Марголин, Б. З.; Kostylev, V. I.; Ilyin, A. V.; Minkin, A. J.

doi:10.1016/s0308-0161(01)00122-3

Cited by 16 publications

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“…To verify this assumption, we carried out the calculation of predicted ε f in ductile failure, using the model [25,26]. The input data for the calculation were the parameters that describe the true failure diagram, the parameters A ρ and ρ f that represent the void nucleation at inclusions, and the triaxiality of the stress state [25,26].…”

Section: Analysis Of Plasticity ε F Of Materials Irradiated At Varioumentioning

confidence: 99%

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Embrittlement and fracture toughness of highly irradiated austenitic steels for vessel internals of WWER type reactors. Part 2. Relation between irradiation swelling and irradiation embrittlement. Physical and mechanical behavior

et al. 2010

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The mechanical test results and fractographic observations reported in Part 1 are discussed from the standpoint of possible fracture mechanisms in austenitic steels subjected to intensive neutron irradiation. We put forward the mechanisms that relate the γ α → -transformation to the occurrence of a ductile-brittle transition in the irradiated austenitic steels and presents a criterion that defines the irradiation conditions whereby the γ α → -transformation leads to the ductile-brittle transition.Some possible reasons for the deterioration of the material ultimate strength at a very high (above 20%) level of swelling are discussed.Introduction. Part 1 [1] presented the results of experimental investigations of mechanical properties and irradiation swelling of austenitic steel 08Kh18N10T and its weld metal upon intensive neutron irradiation, which were performed in order to clarify the nature of the effect of the swelling on mechanical properties of austenitic steels.For this study some specimens were irradiated at a "low" temperature (T irr = 330-340°C) with a dose of 46 dpa (hereinafter referred to as the LTI material) and the other at a "high" temperature (T irr = 400-450°C) with a dose of 49 dpa (called the HTI material). These irradiation conditions were chosen for the purpose of producing different levels of swelling in the specimens. Specifically, the irradiation swelling is close to zero in the LTI material and ranges between 3 and 13% in the HTI material.The experimental investigations performed demonstrate that for the base metal the temperature functions σ 0 2 . ( ) T test and σ u test T ( ) are almost equidistant for the unirradiated and LTI material. For the HTI irradiated base metal which has a significant irradiation swelling, these functions are not equidistant to those for unirradiated and LTI specimens. However, for the weld metal they are equidistant for all three material states studied. We noted a significant increase in plasticity of the HTI material in comparison to that of the unirradiated material and the HTI material. At T test ≤°200 C the plasticity of the base metal upon HTI is close to zero.It was suggested in [1] that the base metal upon HTI undergoes an γ α → phase transformations.

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Section: Analysis Of Plasticity ε F Of Materials Irradiated At Varioumentioning

confidence: 99%

“…The input data for the calculation were the parameters that describe the true failure diagram, the parameters A ρ and ρ f that represent the void nucleation at inclusions, and the triaxiality of the stress state [25,26].…”

Section: Analysis Of Plasticity ε F Of Materials Irradiated At Varioumentioning

confidence: 99%