Radiation embrittlement modelling for reactor pressure vessel steels: I. Brittle fracture toughness prediction

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

doi:10.1016/s0308-0161(99)00042-3

Cited by 30 publications

(34 citation statements)

References 23 publications

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“…6. The values of ΔT F vs. nickel content for 15Kh2NMFA-A with constant phosphorus and copper contents [19]. notation is the same as in Fig.…”

Section: Analysis Of Influence Of Alloying Elements On a F The Consmentioning

confidence: 99%

“…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%

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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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“…6. The values of ΔT F vs. nickel content for 15Kh2NMFA-A with constant phosphorus and copper contents [19]. notation is the same as in Fig.…”

Section: Analysis Of Influence Of Alloying Elements On a F The Consmentioning

confidence: 99%

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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“…It was also demonstrated in [24,25] that the prediction of fracture toughness for irradiated RPV steels by RKR and Beremin models would be incorrect. Indeed, according to the models the temperature dependence of fracture toughness K T Jc ( ) is governed by the temperature dependence of yield stress σ Y T ( ) [see Eq.…”

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confidence: 99%

“…(3)], because the brittle fracture critical stress is temperature-independent and the strain hardening coefficients show only weakly dependent on temperature. For RPV steels in the operating temperature range 20 300 ≤ ≤°T C the yield stress varies rather slightly [24,25]. Then, for these steels with a high transition temperature (the change from the lower to the upper shelf of K T Jc ( ) takes place within the RPV operating temperature range, e.g., for an irradiated steel) the models will predict a very weak temperature dependence of fracture toughness, which is inconsistent with the experimental data.…”

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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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Radiation embrittlement modelling in multi-scale approach to brittle fracture of RPV steels

2012

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Radiation embrittlement modelling for reactor pressure vessel steels: I. Brittle fracture toughness prediction

Cited by 30 publications

References 23 publications

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

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

Radiation embrittlement modelling in multi-scale approach to brittle fracture of RPV steels

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