The contribution of grain boundary effects to low-alloy steel irradiation embrittlement

Nikolaeva, A. V.; Nikolaev, Yu. A.; Kryukov, A.

doi:10.1016/0022-3115(94)00361-0

Cited by 44 publications

(22 citation statements)

References 23 publications

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“…Also, a phosphorus content greater than 0.02 wt% negatively affects the mechanical properties of the material [16] because it increases the brittleness of the material at higher temperatures. In addition, Petrequin et al [17], Stofanak et al [18] and Nikolaeva et al [19] concluded that no negative effect on the material properties was observed for a nickel content less than 1 wt %. Similarly, vanadium increases the susceptibility of the material to neutron irradiation embrittlement [8][9][10]14].…”

Section: Previous Analysis: Review Of Influence Of Copper Phosphoroumentioning

confidence: 99%

New Decision Methodology for Selecting Manufacturing Codes of Nuclear Reactor Pressure-Vessels

Rodríguez-Prieto¹,

Camacho²,

Sebastián³

2016

DAAAM Proceedings

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An innovative methodology based on stringency matrixes is proposed in this paper as a decision tool among materials specifications; thus, this selection method helps in the stage of the structural materials selection used in the reactor pressure vessels (RPV) manufacturing. This paper quantifies the stringency of materials requirements by application of a decision deterministic algorithm based on a stringency matrixes system. The methodology has been applied to different standardized materials used in nuclear design, such as SA -533 Grade B Cl.1, SA -508 Cl.3 (specified by American society of mechanical engineers -ASME code), DIN 20MnMoNi55 (as described in KTA rules) and 16MND5 (issued by French nuclear commission, RCC-MR code) specifications. Key scientific publications on the influence of chemical composition on the mechanical behaviour of materials have been considered as an additional element of judgement. The final results show that steel specified by KTA is the best option.

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Section: Previous Analysis: Review Of Influence Of Copper Phosphoroumentioning

confidence: 99%

New Decision Methodology for Selecting Manufacturing Codes of Nuclear Reactor Pressure-Vessels

Rodríguez-Prieto¹,

Camacho²,

Sebastián³

2016

DAAAM Proceedings

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“…[3,[5][6][7][8] Irradiation hardening, which facilitates the growth of a brittle crack by suppressing dislocation activities near the crack tip, is a common problem for a variety of RPV steels, and P segregation weakens grain boundaries in RPV steels such as the C-Mn steel and the 2 1 4 Cr-1Mo steel, but does not produce much grain-boundary weakening in the A533B steel.…”

Section: Introductionmentioning

confidence: 99%

Mechanisms of Neutron Irradiation Hardening in Impurity-Doped Ferritic Alloys

Nishiyama

Liu

Kameda

2008

Metall Mater Trans A

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Mechanisms of neutron irradiation hardening in phosphorus (P)-doped, sulfur (S)-doped, and copper (Cu)-doped ferritic alloys have been studied by applying a rate theory to the temperature dependence of the yield strength. Hardening behavior induced by neutron irradiation at various temperatures (473 to 711 K) is characterized in terms of the variations in athermal stress and activation energy for plasticity controlled by precipitation or solid solution, and kink-pair formation with the content and type of impurities. In P-doped alloys, neutron irradiation below 563 K brings about a remarkable increase in the athermal stress and activation energy, due to the dispersion of fine (~1.7-nm) P-rich precipitates that is more extensive than that for the Cu-rich precipitates reported in irradiated steel. During neutron irradiation above 668 K, precipitation hardening occurs to some extent in Cu-doped and S-doped alloys, compared to small or negligible hardening in the P-doped alloys. In alloys with a low to moderate content of various dissolved impurities subjected to high-temperature irradiation, the formation of kink pairs becomes considerably difficult. Differing dynamic interactions of dissolved and precipitated impurities, i.e., P and Cu, with the nucleation and growth of dislocations are discussed, giving rise to irradiation hardening.

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“…The phosphorous requirements of all options-excepting KTA 20MnMoNi55 and SA-533 Gr.B Cl.1-are not sufficient according to the experimental limits [1]. The nickel requirement of ASME SA-508 Gr.2, DIN 22NiMoCr37, ASME SA-508 Cl.3, and JIS G-3204 SFVQ1A is also insufficient according to the experimental limits [35,43]. Regarding vanadium requirement, KTA-DIN 20MnMoNi55 and RCC 16MND5 exhibit the highest stringency level.…”

Section: Rodríguez-prieto Et Almentioning

confidence: 99%

“…Ni Some studies [35,43] have concluded that no negative effect on the material properties was observed for a nickel content less than 1 wt %.…”

Section: Ndmentioning

confidence: 99%

“…Once the requirements are selected, they are classified into two main groups, chemical impurities (cases 1 and 2) and mechanical requirements and alloy elements (case 3). Case 2 (Equations 4-8) is used for evaluating copper, nickel and phosphorous contents according to the experimental limit (L e ) stated by key research works [1,35,36,43]; thus, case 1 (Equation 2) is used for evaluating silicon and vanadium contents.…”

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confidence: 99%

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An educational software to reinforce the comprehensive learning of materials selection

Rodríguez-Prieto

Camacho

Merayo

et al. 2017

Comp Applic In Engineering

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An educational software, called CalSev 1.0.2, has been developed for supporting the teaching in materials selection seminars. As a case study, a selection of materials for nuclear reactor pressure vessels has been chosen, because it is a representative example of the relationship between chemical composition, mechanical properties, and in-service behavior. This software has been developed to improve the students' understanding of the materials selection tasks, providing an interactive user-friendly platform that allows to modify-in real time-the content of chemical elements and mechanical requirements to obtain a materials performance evaluation. Due to its versatility, this informatics tool represents a great value for educational purposes, with special impact in blended and distance learning, by simplifying the arduous task of materials selection for a wide range of applications and promoting a collaborative working environment by easing the creation of small groups analyzing different study cases. Finally, to evaluate the functionality, interest, user-friendliness and the educational characteristics of CalSev 1.0.2, a survey among 36 undergraduate students has been carried out. K E Y W O R D Scomprehensive learning, computer-aided tool, educational support, materials selection, materialsEngineering is a practicing profession devoted to harnessing and modifying the three fundamental resources that humankind has available for the creation of all technology: energy, materials, and information [19]. In addition, nowadays, engineers need access to material attributes data and, since the quantity of data is large and the methods tedious to implement by hand, computer-based tools are necessary to enable the right selection of materials depending on the application [5].Selection of suitable materials for a given component is thus one of the hardest tasks to perform and hence, designers need to put their utmost effort in identifying the best materials with specific functionalities to fulfill the application requirements [39]. Design of components is associated with the Abbreviations: ASME B&PV, American society of mechanical engineers boiler and pressure vessels; JSME, Japanese society of mechanical engineers; KTA, Kerntechnischer Ausschuss (German nuclear commission); L e , experimental limit provided by key works; L s , standardized limit as described by the manufacturing codes; L s (Min) , minimum value of the standardized limits; L s (Max) , maximum value of the standardized limits; PWR, pressurized water reactors; RCC-MR, French code of nuclear design; RPV, reactor pressure vessels; SL/SLM, stringency level/stringency level methodology; SL (Max) , maximum stringency level; UTS, ultimate tensile strength (minimum required value); WORA, write once, run anywhere; XML, eXtensible markup language; Y p , yield point (minimum required value); σ max , maximum standard deviation.Comput Appl Eng Educ. 2018;26:125-140.wileyonlinelibrary.com/cae

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The contribution of grain boundary effects to low-alloy steel irradiation embrittlement

Cited by 44 publications

References 23 publications

New Decision Methodology for Selecting Manufacturing Codes of Nuclear Reactor Pressure-Vessels

New Decision Methodology for Selecting Manufacturing Codes of Nuclear Reactor Pressure-Vessels

Mechanisms of Neutron Irradiation Hardening in Impurity-Doped Ferritic Alloys

An educational software to reinforce the comprehensive learning of materials selection

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