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Proceeding Paper

Work-Hardening Behavior of Cold Rolled EUROFER97 Steel for Nuclear Fusion Applications †

1
Dipartimento di Ingegneria Industriale, Università di Roma ‘‘Tor Vergata’’, 00133 Roma, Italy
2
Dipartimento di Ingegneria, Università di Perugia, 06125 Perugia, Italy
3
CALEF-ENEA CR-Casaccia, Via Anguillarese 301, 00123 S. Maria di Galeria, Rome, Italy
4
RINA Consulting Centro Sviluppo Materiali, Via di Castel Romano 100, 00128 Roma, Italy
*
Author to whom correspondence should be addressed.
Presented at the 1st International Electronic Conference on Metallurgy and Metals, 22 February–7 March 2021; Available online: https://iec2m.sciforum.net/.
Mater. Proc. 2021, 3(1), 21; https://doi.org/10.3390/IEC2M-09242
Published: 18 February 2021
(This article belongs to the Proceedings of The 1st International Electronic Conference on Metallurgy and Metals)

Abstract

:
The reduced activation martensitic steel EUROFER97 is recognized in Europe as the reference steel for structural applications in future nuclear fusion reactors. Usually, EUROFER97 steel plates are manufactured by hot rolling and successive heat treatments: (1) austenitization at 980 °C for 30 min, (2) air cooling, and (3) tempering at 760 °C for 90 min. Recently, thermo-mechanical treatments have been investigated by us with the scope to improve the mechanical properties, namely, to strengthen the steel without reducing its ductility. The experiments involve cold rolling with three reduction rates (30%, 40%, 50%) and, for each of them, heat treatments at different temperatures in the range from 550 °C to 750 °C. The mechanical and microstructural characterization of the samples after successive stages of the process is now underway and present work reports some preliminary results. The characteristics of the samples after cold rolling have been examined by means of hardness tests, metallography, and X-ray diffraction measurements, and work-hardening is discussed in terms of dislocation density.

1. Introduction

Reduced-activation ferritic-martensitic (RAFM) steels, variants of conventional ferritic-martensitic steels, were developed to be used as structural materials in future nuclear fusion reactors and generation IV nuclear fission reactors [1,2].
EUROFER97 is the reference RAFM steel in Europe [1] for the test blanket module in ITER reactor [3] and for structural sections subjected to high radiation energy in DEMO: first wall, divertor, blanket, vessel [4,5,6,7].
The chemical composition of EUROFER97 steel was suitably modified to simplify the storage of radioactive waste after the disassembly of the reactor [8]. Some alloying elements commonly present in Cr-Mo steels were replaced with equivalent elements having a faster induced radiation decay [9]. The Mo was replaced with W and the Nb with Ta e V. Furthermore, other elements such as Ni, Nb, Mo, Cu, and N were kept as low as possible [10].
When steels undergo neutron radiation, cascades of atomic displacements are generated [11] and He is produced by transmutation reaction [12]. Lattice defects, produced by atomic displacement, lead to a variation of the microstructure and micro composition with consequent dimensional instability and degradation of the mechanical proprieties. EUROFER97 steel is traditionally produced by means of a hot-rolling process and subsequent heat treatment [5,13]: austenitizition at 980 °C for 30 min, air cooling, and tempering at 760 °C for 90 min [4]. This allows achievement of a tempered martensitic microstructure. Henceforth this state of the steel will be referred to as standard EUROFER97 in comparison with the variant states investigated during the activity.
Based on the irradiation experiment conducted so far, EUROFER97 has shown good performance in the temperature range from 350 °C to 550 °C [13,14]. Several studies have been conducted aimed to enlarge the operating temperature range for this steel [15,16]. The upper limit at 550 °C is imposed by swelling and irradiation creep. To date, a possible solution to raise the maximum operating temperature is through an oxide dispersion strengthen (ODS) variant of EUROFER97 steel.
EUROFER97-ODS was fabricated by mechanical alloying of yttrium oxide powders (Y2O3 at 0.3 wt.%) [1,14,16]. The presence of fine, grain size, and nanometric-scale oxide particle [17] leads to an increase in mechanical performance at temperatures above 550 °C [18]. Instead, regarding lower temperature limit, this depends on the loss of ductility. The lattice defects produced by neutron radiation, at temperature below and up to 350 °C, lead to an increase of Ductile-Brittle Temperature Transition (DBTT) [14]. Therefore, lowering the DBTT before irradiation would allow a lowering of the minimum operating temperature. It is well known that the only process that decreases the DBTT is the refinement of the grain size [19,20,21]. Moreover, a refinement of the microstructure would show many advantages in the nuclear application [14]. In literature, it was shown that a particularly fine microstructure, on micro and nanometric scale, obtained by hot or cold mechanical process followed by annealing, gives high mechanical strength (the grain boundaries limit the dislocation movement) and give high resistance to radiation [4,19]. The greater surface of grain boundaries guarantees more recombination centers of point defects [2] and lower susceptibility to He [2,22]. In literature, various strategies have been studied for the grain size strength on EUROFER97 steel both during austenitization phase (reduction of prior austenitic grain) [22] and in the tempering phase [13]. In this paper, the effect of a thermo-mechanical process on the microstructure of EUROFER97 steel is reported with the aim to improve the tensile properties and to evaluate the possible application in the fusion nuclear reactors. In particular, the work-hardening behavior was investigated after a cold-rolling process and compared with traditional EUROFER97 steel. The characterization was carried out by means of hardness test, metallography, and X-ray diffraction measurements.

2. Material and Methods

The nominal steel chemical composition of EUROFER97 is reported in Table 1.
The EUROFER97 steel in the standard condition was subjected to cold rolling followed by recrystallization heat treatment. In particular, three different cold reduction (CR) ratios (30%, 40%, 50%) were investigated.
In this work, the microstructure of standard EUROFER97 and after cold-rolling process was analyzed and compared using a high-resolution electronic scanning microscope (FE-SEM Zeiss, Gemini Supra 25). Moreover, Vickers hardness (HV5) tests and X-ray diffraction measurements were carried out to estimate dislocation density.
Dislocation density (ρ) was calculated from local micro-strain (ε) using Williamson-Smallman relation (1) [23].
The micro-strain ε was estimated by full width at half maximum (FWHM) of the X-ray diffraction peak [24].
ρ = 14.4 ∗ ε2 ∗ b−2
where b is the burger vector (b ≈ 0.25 nm).
X-ray diffraction spectra were obtained with Mo-Kα radiation (λ = 0.703 Å) and precision spectra were conducted with angular steps of 2θ = 0.005 and counting time for step of 4 s. For the estimation of ε, the kα1 component of the {100} line of the spectrum was used.

3. Results and Discussion

The effect of cold plastic deformation on EUROFER97 microstructure is clearly visible in SEM images as shown in Figure 1. In particular, in Figure 1a, prior austenite grains and laths decorated by carbides, as typical of tempered martensite, are clearly detectable. The effect of cold rolling on tempered martensite is reported in Figure 1b–d. Such figures show a grain shape change: as a matter of fact, the grains become elongated as the CR ratio increases.
The kα1 component of the {100} line as obtained by X-ray diffraction measurements is reported in Figure 2 for EUROFER97 in standard conditions and after cold-rolling process. In Figure 2, all the reported peaks intensities are normalized. Results reported in Figure 2 show a diffraction peaks broadening following the CR ratio increase. Such broadening is an index of the micro-strain increase (and thus the dislocation density). Based on such peaks broadening, dislocation density variation as a function of plastic deformation amount has been calculated according to Equation (1). Dislocation density and hardness values as a function of CR are reported in Figure 3. Results show that an increase of CR from 0 to 50% implies an increase of dislocation density from 7 × 1010 to about 3 × 1011 cm−2. Such increase appears to be quite powerful in terms of hardness variations, leading to a strong HV increase (from 200 HV up to 280 HV in the case of the 50 % cold-rolled material). Such effect appears to be very promising in terms of response to forthcoming heat-treatment effect. In particular, preliminary results carried out on a cold-rolled material showed the possibility to achieve very fine microstructures (about 200 nm grain size) after proper heat treatment [25].

4. Conclusions

In this paper, the effect of cold rolling in terms of work-hardening on EUROFER97 steel is reported. Three different cold reduction ratios (CR) (30%, 40%, 50%) were investigated and, for each ratio, microstructure analysis, Vickers hardness test, and dislocation density measurement were performed. The results obtained for cold-rolled steel was compared to the EUROFER97 steel in the standard condition. Results show that the increase of CR from 0 to 50% leads to an increase of dislocation density from 7 × 1010 to about 3 × 1011 cm−2. Such increase appears to be quite powerful in terms of hardness variations; there is a HV increase from 200 HV for CR: 0%, up to 280 HV in the case of CR: 50%.
These results are promising for fusion nuclear application and can be used as a starting point for more investigation in order to understand the real effect of the complete thermo-mechanical process carried out on the mechanical and irradiation performance of EUROFER97 steel.

References

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Figure 1. SEM images of (a) standard EUROFER97 state, (b) cold-rolled EUROFER97 steel with cold reduction (CR): 30%, (c) cold rolled EUROFER97 steel with CR: 40%, and (d) cold rolled EUROFER97 steel with CR: 50%.
Figure 1. SEM images of (a) standard EUROFER97 state, (b) cold-rolled EUROFER97 steel with cold reduction (CR): 30%, (c) cold rolled EUROFER97 steel with CR: 40%, and (d) cold rolled EUROFER97 steel with CR: 50%.
Materproc 03 00021 g001
Figure 2. Effect of the cold-rolling process on the line shape of {100} X-ray diffraction peak of EUROFER97 steel.
Figure 2. Effect of the cold-rolling process on the line shape of {100} X-ray diffraction peak of EUROFER97 steel.
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Figure 3. Effect of CR on Vickers hardness (HV5) and dislocation density calculated by Williamson-Smallman relation (1) of EUROFER97 steel.
Figure 3. Effect of CR on Vickers hardness (HV5) and dislocation density calculated by Williamson-Smallman relation (1) of EUROFER97 steel.
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Table 1. Nominal steel chemical composition of EUROFER97 (wt.%) (Fe to balance).
Table 1. Nominal steel chemical composition of EUROFER97 (wt.%) (Fe to balance).
CrCMnVWTaTiN
8.930.120.470.21.070.140.0090.018
PSBSiNbMoNiCu
<0.0050.004<0.0010.0060.0020.00150.0020.003
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MDPI and ACS Style

Stornelli, G.; Schino, A.D.; Montanari, R.; Testani, C.; Varone, A.; Mancini, S. Work-Hardening Behavior of Cold Rolled EUROFER97 Steel for Nuclear Fusion Applications. Mater. Proc. 2021, 3, 21. https://doi.org/10.3390/IEC2M-09242

AMA Style

Stornelli G, Schino AD, Montanari R, Testani C, Varone A, Mancini S. Work-Hardening Behavior of Cold Rolled EUROFER97 Steel for Nuclear Fusion Applications. Materials Proceedings. 2021; 3(1):21. https://doi.org/10.3390/IEC2M-09242

Chicago/Turabian Style

Stornelli, Giulia, Andrea Di Schino, Roberto Montanari, Claudio Testani, Alessandra Varone, and Silvia Mancini. 2021. "Work-Hardening Behavior of Cold Rolled EUROFER97 Steel for Nuclear Fusion Applications" Materials Proceedings 3, no. 1: 21. https://doi.org/10.3390/IEC2M-09242

APA Style

Stornelli, G., Schino, A. D., Montanari, R., Testani, C., Varone, A., & Mancini, S. (2021). Work-Hardening Behavior of Cold Rolled EUROFER97 Steel for Nuclear Fusion Applications. Materials Proceedings, 3(1), 21. https://doi.org/10.3390/IEC2M-09242

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