Embrittlement of low copper VVER 440 surveillance samples neutron-irradiated to high fluences

Miller, M.K.; Russell, K.F.; Kočík, J.; Keilová, E.

doi:10.1016/s0022-3115(00)00240-3

Cited by 73 publications

(42 citation statements)

References 6 publications

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“…In addition, no copper-enriched precipitates were observed and the copper was found to remain in solid solution in the matrix of some low copper level (0.05-0.06 at. % Cu) 15Kh2MFA base and 10KhMFT welds after neutron irradiation [12]. The copper level decreases slightly and the copper-enriched precipitates were found to increase in size after a post irradiation anneal of 168 h at 454°C.…”

Section: Matrix Compositionsmentioning

confidence: 94%

“…Systematic measurements of the composition of the matrix after exposure to neutron irradiation and annealing treatments have been obtained from several different types of pressure vessel steels [9][10][11][12]. These measurements accurately reflect the true solute content of the matrix since the spatial resolution of the atom probe is sufficient to detect and eliminate any contributions from ultra-fine precipitates, clusters and solute segregation.…”

Section: Matrix Compositionsmentioning

confidence: 99%

“…Significant increases were found in the ductile-to-brittle transition temperature (DBTT), yield and ultimate tensile strengths and reductions were found in the elongation and reduction in area in both low copper (~0.06 a. % Cu) 15Kh2MFA base and 10KhMFT weld surveillance specimens after neutron irradiation at 270°C for 10 years to a fluence of 1.0 x 10 25 m -2 (E > 0.5 MeV) for the base material and at 275 °C for 5 years to a fluence of 5.2 x 10 24 m -2 (E > 0.5 MeV) for the weld, as shown in Table 3 [12]. These changes were not observed in the same material thermally annealed for similar times at 295°C.…”

Section: Solute Segregation To Dislocationsmentioning

confidence: 99%

“…Summary of the mechanical properties of the low copper (~0.06 a. % Cu) 15Kh2MFA base and 10KhMFT weld surveillance specimens for the unirradiated, thermally aged and neutron-irradiated conditions [12] The elongation A 10 is given. …”

Section: Solute Segregation To Dislocationsmentioning

confidence: 99%

See 3 more Smart Citations

Atomic Level Characterization of Neutron Irradiated Pressure Vessel Steels

Miller

Pareige

2000

MRS Proc.

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Atom probe tomography provides one of the most effective tools to characterize the solute distribution and precipitation that occurs in pressure vessel steels and associated model alloys during irradiation. The three-dimensional atom probe is able to experimentally determine the elemental identities of the atoms and their spatial coordinates with near atomic resolution so that their distribution within small volumes of the specimen can be reconstructed and analyzed. This technique together with conventional atom probe field ion microscopy has been applied to many different types of pressure vessel steels and model alloys and has revealed and characterized several different nanostructural transformations. These radiation induced or enhanced processes lead to the formation of copper-nickel-manganese-silicon precipitates, and solute segregation to dislocations, dislocation loops, nanovoids and boundaries.

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Section: Matrix Compositionsmentioning

confidence: 94%

Section: Matrix Compositionsmentioning

confidence: 99%

Section: Solute Segregation To Dislocationsmentioning

confidence: 99%

Section: Solute Segregation To Dislocationsmentioning

confidence: 99%

See 2 more Smart Citations

Atomic Level Characterization of Neutron Irradiated Pressure Vessel Steels

Miller

Pareige

2000

MRS Proc.

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“…It is necessary to note also that P also segregates on dislocation loops and precipitations [19,31,32]. Such segregations hardly affect material hardening [10].…”

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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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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Atom probe tomography characterization of solute segregation to dislocations

Miller

2006

Microscopy Res & Technique

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The extent and level of solute segregation to individual dislocations may be quantified by atom probe tomography. The technique is best applied to materials with high dislocation densities, such as cold worked, mechanically alloyed, or neutron-irradiated materials. Dislocations may be observed in field ion images by a change of the normal concentric atom terraces at crystallographic poles to spirals. Solute segregation is evident in field ion images by brightly imaging atoms near the core of the dislocation. Dislocations are evident in atom maps in the three-dimensional atom probe by linear regions of enhanced solute concentration. The maximum separation envelope and tracer methods may be used to quantify the levels of solute at the dislocation at the subnanometer scale. Examples of interstitial and substitutional element segregation in a mechanically alloyed, oxide dispersion strengthened ferrite steel and phosphorus segregation to dislocations in neutron-irradiated pressure vessel steels are presented.

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Embrittlement of low copper VVER 440 surveillance samples neutron-irradiated to high fluences

Cited by 73 publications

References 6 publications

Atomic Level Characterization of Neutron Irradiated Pressure Vessel Steels

Atomic Level Characterization of Neutron Irradiated Pressure Vessel Steels

On the Modelling of Thermal Aging through Neutron Irradiation and Annealing

Atom probe tomography characterization of solute segregation to dislocations

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