Prometey local approach to brittle fracture: Development and application

Марголин, Б. З.; Shvetsova, V. A.; Gulenko, A. G.; Kostylev, V. I.

doi:10.1016/j.engfracmech.2007.05.002

Cited by 53 publications

(20 citation statements)

References 21 publications

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“…Neutron irradiation leads to the formation of point defects, dislocation loops, precipitates and also leads to the formation of P segregations on the intragranular interphase boundaries and GBs. Microcracks resulting in brittle fracture cannot be nucleated on point defects, dislocation loops, and precipitates as these microcracks are much larger than sizes of these radiation defects [26,27]. erefore, the role of these radiation defects is hardening of material (increase of σ Y ) that results in embrittlement due to increase of stresses near notch or crack tip in specimen.…”

Section: Discussionmentioning

confidence: 99%

“…It means that P does not form new additional barriers for moving dislocations. At the same time, P segregations decrease the strength of interphase boundaries (e.g., carbidematrix boundaries) or grain boundaries that makes the initiation of cleavage microcracks or intergranular brittle microcracks easier and, as a consequence, leads to material embrittlement [3,19,[26][27][28][29]. Since the above mechanism of material embrittlement does not result in its hardening, such an embrittlement mechanism is referred to as a nonhardening mechanism [26,27,30].…”

Section: Introductionmentioning

confidence: 99%

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On the Modelling of Thermal Aging through Neutron Irradiation and Annealing

Марголин

Yurchenko

Potapova

et al. 2018

Advances in Materials Science and Engineering

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A new method predicting long-term thermal embrittlement of steel caused by P segregation is verified. e method is based on the results of impact strength or fracture toughness tests using specimens after relatively short-term neutron irradiation followed by annealing. 2Cr-Ni-Mo-V steel used in reactor pressure vessels of WWER-1000 type is investigated in four conditions: initial condition, after thermal aging, after neutron irradiation, and postirradiation annealing. e results of impact strength and tensile tests and SEM investigation are presented. e brittle fracture features are considered for different material conditions. Calculative estimation on neutron irradiation effect on P diffusion in steels is carried out. Experimental data are reported which confirm an intense P diffusion acceleration under neutron irradiation.

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Section: Discussionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

On the Modelling of Thermal Aging through Neutron Irradiation and Annealing

Марголин

Yurchenko

Potapova

et al. 2018

Advances in Materials Science and Engineering

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“…Noteworthy is that chemical elements have an influence on the material embrittlement not only through the formation of clusters and hardening but also via the occurrence of segregates that suppress the initiation of cleavage microcracks [9,12,17,[19][20][21][22]. In particular, the phosphorus segregates localized at the interfaces (e.g., at the carbide-matrix boundaries) or at the grain boundaries impair the material resistance to microcracking.…”

Section: Introductionmentioning

confidence: 99%

A new approach to description of in-service embrittlement of WWER-1000 reactor pressure vessel materials

et al. 2010

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Based on available published data and experimental findings, the in-service embrittlement of materials has been analyzed. The contributions of thermal ageing and neutron irradiation to embrittlement of the base and weld metals of WWER-1000 reactor pressure vessels are discussed. Equations have been derived which describe the shift of the critical brittle temperature depending on the irradiation time and neutron fluence. For a nickel-rich weld metal a relation between the radiation embrittlement coefficient and the amount of alloying elements Ni, Mn, and Si has been defined.Keywords: embrittlement, reactor pressure vessel, shift of critical brittle temperature, irradiation, neutron fluence. Introduction. Investigations [1-25] of embrittlement behavior of WWER-1000 reactor pressure vessel (RPV) materials [the base metal (BM) is 15Kh2NMFA-A steel and the weld metal (WM) -the weld joints of steel 15Kh2NMFA-A] give rather conflicting findings. This applies primarily to the description of the shift of the critical brittle temperature ΔT k k as a function of the neutron fluence [1]:

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“…For calculating the brittle fracture characteristics on a macrolevel, including the fracture toughness, a probabilistic model was elaborated based on the local criterion (4); it is known as the Prometey model [22,[30][31][32] and, like the Beremin model, involves the Weibull statistics. The Prometey model was developed in two modifications: with a single stochastic parameter (σ d [22]) and two stochastic parameters (S c and σ d [31,32]).…”

mentioning

confidence: 99%

“…The Prometey model was developed in two modifications: with a single stochastic parameter (σ d [22]) and two stochastic parameters (S c and σ d [31,32]). …”

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confidence: 99%

Brittle fracture local criterion and radiation embrittlement of reactor pressure vessel steels

et al. 2010

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The application of local criteria for predicting brittle fracture of reactor pressure vessel steels is discussed with an emphasis on radiation embrittlement. An association of the radiation-induced damages and the processes of initiation and propagation of cleavage microcracks is analyzed from the standpoint of the local criterion for fracture. Physical-mechanical models are put forward to describe the influence of radiation damages on the cleavage microcrack initiation. The influence of the material hardening caused by neutron irradiation and plastic deformation on the fracture toughness is studied.Introduction. The intensive development of the local criterion over the last three decades has been caused mostly by the need for adequate prediction of fracture toughness of irradiated materials of nuclear reactor pressure vessels. It is common knowledge that embrittlement of reactor pressure vessel (RPV) materials is assessed by the test results for surveillance specimens. The surveillance specimen programs usually involve irradiation and testing of small-sized specimens only. It has been also known that to determine the temperature dependence of fracture toughness K T Jc ( ) one should perform tests on sufficiently large specimens (full-size specimens) over a wide temperature range. Thus, there arises a problem in principle: how to determine K T Jc ( ) for an irradiated steels from the test results for small-size specimens.The most promising solution to this problem is to use a so-called local approach to predicting fracture toughness of irradiated RPV materials. The local approach can be defined as a method of predicting fracture characteristics on the macrolevel in terms of mechanical parameters using a local criterion for fracture. Clearly, the local approach is based on the local criterion for brittle fracture. The critical parameters involved in the criterion can be related, in principle, to the physical mechanisms of initiation and propagation of microdamages, in this case the cleavage microcracks.At present, there are several available definitions of the local criterion for brittle fracture. The conventional one is written as [1][2][3][4][5][6] σ σ

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Prometey local approach to brittle fracture: Development and application

Cited by 53 publications

References 21 publications

On the Modelling of Thermal Aging through Neutron Irradiation and Annealing

On the Modelling of Thermal Aging through Neutron Irradiation and Annealing

A new approach to description of in-service embrittlement of WWER-1000 reactor pressure vessel materials

Brittle fracture local criterion and radiation embrittlement of reactor pressure vessel steels

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