Low cycle thermomechanical fatigue of reactor steels: Microstructural and fractographic investigations

Fekete, Balázs; Kasl, Josef; Jandová, Dagmar; Jóni, Bertalan; Misják, F.; Trampus, Péter

doi:10.1016/j.msea.2015.05.093

Cited by 13 publications

(4 citation statements)

References 24 publications

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“…Many research papers discuss the heat treatment of stabilized austenitic stainless steels. Publications have very often dealt with the HT of parts after welding [4][5][6][7], corrosion resistance (especially intercrystalline corrosion) [8][9][10][11], fatigue properties [12][13][14], or the mechanical properties of commercial steel AISI321 [15][16][17]. However, what is not very common in the literature is the issue of the HT of stabilized grades in order to increase their mechanical characteristics, especially the cold and hot yield strength (YS) and ultimate tensile strength (UTS) [18].…”

Section: Introductionmentioning

confidence: 99%

Influence of Higher Stabilization Temperatures on the Microstructure and Mechanical Properties of Austenitic Stainless Steel 08Ch18N10T

Janda

Jeníček

Opatová

et al. 2023

Metals

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Precipitation strengthening in titanium-stabilized austenitic stainless steels can improve the hot yield strength, as requested, e.g., for nuclear industry applications. The resulting properties depend mainly on the parameters of the heat treatment and previous forming. The influence of the heat treatment parameters on the development of the microstructure and mechanical properties was determined for steel 08Ch18N10T (GOST). Solution annealing and stabilization with different temperatures and holds were performed on the steel, which was, in delivered condition, stabilized at 720 °C. Heat-treated samples were subjected to static tensile testing at room temperature and at 350 °C, microstructural analysis using light, scanning electron and transmission electron microscopy focused on precipitates, and HV10 hardness testing. The strengthening mechanism and its dependence on the stabilization parameters are described. The results of the experiment show the influence of the state of the input material on the final effect of heat treatment—repeated heat treatment achieved lower-strength characteristics than the initial state, while almost all modes showed above-limit values for the mechanical properties. Stabilization temperatures of 720 to 800 °C were found to be optimal in terms of the achieved hot yield strength. At higher temperatures, slightly lower strengths were achieved, but at significantly shorter dwell times.

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Section: Introductionmentioning

confidence: 99%

Influence of Higher Stabilization Temperatures on the Microstructure and Mechanical Properties of Austenitic Stainless Steel 08Ch18N10T

Janda

Jeníček

Opatová

et al. 2023

Metals

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“…This paper deals with the material properties of L-DED fabricated and heat-treated 08CH18N10T material and comparison to conventionally fabricated. The alloy 08CH18N10T has been widely used in many VVER reactors around the world and have been studied in detail [1][2][3][4]. It has been used for both in-core and out-of core components.…”

Section: Introductionmentioning

confidence: 99%

Effect of heat-treatment on material properties of L-DED printed austenistic alloy 08CH18N10T for nuclear reactor applications

Jedlan,

Ševeček,

Prantl

et al. 2023

APP

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This paper deals with the evaluation of material properties of the additively manufactured austenistic alloy 08CH18N10T, which is widely used in the Czech Republic nuclear power plants Temelín and Dukovany and other VVER reactors around the world. For purposes of utilization of additive manufacturing technologies for nuclear core components fabrication, two sets of samples were prepared from horizontally and vertically L-DED printed blocks from 08CH18N10T material. Experiments such as microstructure analysis, porosity and Vickers hardness were then performed on L-DED printed and heat-treated 08CH18N10T material, and the obtained material properties were then compared with the properties of L-DED printed 08CH18N10T material without heat-treatment for examination of its effect and also with material properties of conventionally made 08CH18N10T material.

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“…Generally, isothermal low cycle fatigue (IF) tests performed at the maximum temperature (Tmax) of reactor operation, are used to assess the performance of materials subjected to TMF loadings, owing to the simplicity associated with the former. However, thermal cycling in association with mechanical deformation has been reported to be more damaging compared to the isothermal mechanical strain cycling even at the Tmax of the TMF cycles [ (Okazaki et al, 2003), (Jaske, 2003), (Nagesha et al, 2010), (Cheng et al, 1973), (Suresh Kumar et al, 2019), (Beck et al, 1997), (Fekete et al, 2015)] .…”

Section: Introductionmentioning

confidence: 99%

A study of isothermal mechanical fatigue of welded reactor steel (15H2MFA)

Keba

Thanganadar²,

Abishini³

2022

Int J Adv Manuf Technol

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In material science and engineering the fatigue of metal is quite di cult to deal with and that of welded joint is an even more complex phenomenon. This complexity arises from different main factors: thermal cycles during welding, which will strongly affect the base material and induce residual stresses and distortion, the fusion process with the ller metal leads to heterogeneity to microstructure which will affect or change the original mechanical properties and chemical composition through out of the welded joint. In this study isothermal mechanical fatigue of welded reactor steel has been contemplated. The samples of the welded joint have used in this study is 15H2MFA steel type of VVER-440 reactor pressure vessel operating at Paks Nuclear Power Plant, Hungary. The reactor vessel is made of low-alloy heat resistant steel and austenitic steel with a corrosion-resistant inner (clad) surface. Reactor pressure vessel (RPV) made of 2 ¼ Cr -1Mo-V bainitic steel having a good mechanical strength and creep resistance.

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Low cycle thermomechanical fatigue of reactor steels: Microstructural and fractographic investigations

Cited by 13 publications

References 24 publications

Influence of Higher Stabilization Temperatures on the Microstructure and Mechanical Properties of Austenitic Stainless Steel 08Ch18N10T

Influence of Higher Stabilization Temperatures on the Microstructure and Mechanical Properties of Austenitic Stainless Steel 08Ch18N10T

Effect of heat-treatment on material properties of L-DED printed austenistic alloy 08CH18N10T for nuclear reactor applications

A study of isothermal mechanical fatigue of welded reactor steel (15H2MFA)

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