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Effect of Additional Minor Elements on Accumulation Behavior of Point Defects under Electron Irradiation in Austenitic Stainless Steels

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Effect of Additional Minor Elements on Accumulation Behavior of Point Defects

under Electron Irradiation in Austenitic Stainless Steels

Yoshihiro Sekio

1,+

, Shinichiro Yamashita

1

, Norihito Sakaguchi

2

and Heishichiro Takahashi

1,2 1Oarai Research and Development Center, Japan Atomic Energy Agency, Oarai, Ibaraki 311-1393, Japan

2Center for Advanced Research of Energy Technology, Hokkaido University, Sapporo 060-0808, Japan

Addition of minor elements to a base alloy is often applied with the aim of mitigating void swelling by decreasing the vacancy diffusivity andflux which influence vacancy accumulation behavior. However, the comparative evaluations of parameters, such as the diffusivity andflux, between a base alloy and modified alloys with specific additives have not been studied in detail. In this study, type 316 austenitic stainless steel as a base alloy and type 316 austenitic stainless steels modified with vanadium (V) or zirconium (Zr) additions were used to perform evaluations from the changes of widths of the void denuded zone (VDZ) formed near a random grain boundary during electron irradiation because these widths depend on vacancy diffusivity andflux. The formations of VDZs were observed inin-situobservations during electron irradiation at 723 K and the formed VDZ widths were measured from the transmission electron microscopic images after electron irradiation. As a result, the VDZs were formed in both steels without and with V, and respective widths were³119 and³100 nm. On the other hand, the VDZ formation was not observed clearly in the steel with Zr. From the measured VDZ widths in the steels without and with V addition, the estimated ratio of the vacancy diffusivity in the steel with V to that in the steel without V was about 0.50 and the estimated ratio of the vacancyflux in the steel with V to that in the steel without V was about 0.71. This result suggests that the effect of additional minor elements on vacancy accumulation behaviors under electron irradiation could be estimated from evaluations of the VDZ width changes among steels with and without minor elements. Especially, because void swelling is closely related with the vacancy diffusion process, the VDZ width changes would also be reflected on void swelling behavior. [doi:10.2320/matertrans.MD201309]

(Received September 2, 2013; Accepted November 22, 2013; Published December 28, 2013)

Keywords: austenitic stainless steel, void denuded zone, in-situ observation, electron irradiation

1. Introduction

For the development of nuclear reactor materials, espe-cially austenitic stainless steels, used under high irradiation dose and temperature, it is quite important to suppress irradiation-induced void swelling1­5)which is affected by the accumulation behavior of point defects (self-interstitial atoms (SIAs) and vacancies) induced by high energy particle irradiation. In order to retard the initiation time of steady void swelling and reduce the void swelling rate, minor elements are often added to a base alloy.6,7) Especially, irradiation-introduced point defects strongly interact with added minor elements so that the defect accumulation behavior for the formation of dislocation loops and voids is influenced due to the interaction.8­11)However, the comparative evaluation of the diffusion behavior which affects point defects accumu-lation behavior between steels with and without alloying minor elements has not been investigated.

As a phenomenon which is related to vacancy accumu-lation behavior, it is well known that the void denuded zone (VDZ)12­15)near a random grain boundary (GB) which acts as a neutral sink of point defects is formed with a given width during a steady-state irradiation. Hence, it is expected that VDZ widths formed in alloys containing oversized minor elements which have a strong interaction with irradiation-induced vacancies might vary as a result of vacancy diffusivity andflux changes (vacancy mobility change) due to the interaction. Therefore, it would be expected that the relative effects of alloying elements on the vacancy diffusivity and flux might be estimated from evaluations of the VDZ width changes among steels with and without minor elements. This would allow more detail estimation for the

effect of additional minor elements on the point defect accumulation and void swelling behavior under irradiation. Furthermore, it would provide important information for future alloying design specifications such as the determi-nation of suitable minor elements to suppress void swelling. In the present study, type 316 austenitic stainless steel as a base alloy and type 316 austenitic stainless steels modified with vanadium (V) or zirconium (Zr) additions were used, and the changes of parameters such as vacancy diffusivity and flux among steels with and without additional minor elements were investigated from the measurement of the changes of VDZ width induced during electron irradiation as afirst approach.

2. Experimental Procedure

Materials used were a low carbon type 316 (SUS316L) austenitic stainless steel and two modified SUS316L steels with V or Zr element additions of 0.35 at%. These modified steels were chosen for the reason that each had largely different void swelling behavior as reported by Katoet al.9) so that the changes of vacancy diffusivity and flux by additions of V or Zr elements were also expected to be large. These steels used in this study were the same as those examined by Kato et al.The chemical compositions for the three steels are shown in Table 1. Disks of 3 mm diameter and 0.1 mm thickness were prepared from the SUS316L and the modified SUS316L steels for electron irradiation and were electro-polished after solution-annealing treatment at 1323 K for 30 min. Electron irradiations were carried out using the 1 MV high voltage electron microscope (HVEM) at 723 K to doses up to 14.4 dpa and the formations of VDZs were observed by in-situ observations. The electron irradi-ation conditions are given in Table 2. These irradiirradi-ation

+Corresponding author, E-mail: sekio.yoshihiro@jaea.go.jp

Special Issue onIn SituTEM Observation of High Energy Beam Irradiation

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conditions were chosen to achieve the steady-state in each steel. The irradiation temperature 723 K at which void swellings of these steels are remarkable9) was selected in the present study in order to evaluate the vacancy diffusivity and flux changes among steels more clearly. The electron irradiation regions were selected at random GBs which were identified from selected area electron diffraction patterns. Thicker regions over 300 nm thick including random GBs were selected for the irradiation considering the surface sink effect for point defects. The VDZ widths formed near the GBs were measured from the observed transmission electron microscopic (TEM) images after electron irradiation. Then, the average VDZ widths were determined as the distance between the GB and voids close to the GB. Parameters such as vacancy diffusivity and flux for vacancy accumulation behavior were analyzed from the VDZ widths using equations given by Konobeevet al.14)and Sakaguchiet al.16)

3. Results and Discussion

3.1 In-situobservation of VDZ formation

When the areas including a random GB were electron irradiated to 7.2 dpa in the SUS316L-V steel, the

micro-structural evolutions during electron irradiation were ob-served. Figure 1 shows the typical microstructures. In the early stage of irradiation to 0.1 dpa, the interstitial dislocation loops were nucleated near the GB and in the area away from the GB. Especially, the loop sizes near the GB seemed to be slightly larger than those in the area away from the GB. This can be explained as follows. First, Frenkel point defects of SIAs and vacancies can be introduced by electron irradiation. After that, SIAs with higher mobility compared to vacancies can diffuse preferentially and they can nucleate so that the interstitial dislocation loops can be formed in the whole irradiated area. Consequently, the loops can continue to grow with increasing irradiation dose by absorbing SIAs intro-duced under irradiation, then the loops nucleated near the GB can grow larger compared with those in the area away from GB because the SIAs near the GB preferentially diffuse toward the GB according to the inverse Kirkendall effect.15) Thus, the loop sizes formed near the GB would become larger than those in the area away from the GB.

[image:2.595.56.545.83.329.2]

When the irradiation was increased to 1.0 dpa, the dislocation loops formed near the GB disappeared and the dislocation free zone (DLFZ) was formed. When the dislocation loops nucleate, the concentration of free SIAs is decreased, while the excess vacancy concentration is in-creased.17) Then, the dislocation loops absorb the excess vacancies, and the distribution and sizes of the dislocation loops is significantly changed. Especially, the dislocation loops nucleated near the GB are able to absorb more vacancies because vacancies induced near the GB alsoflow to the GB. Furthermore, the concentration of free SIAs near the GB is also decreased more than that in the area away from the GB so that the nucleation or growth of the dislocation loops is suppressed. Hence, the loops nucleated near the GB in the initial irradiation stage disappeared with increasing

Table 1 Chemical compositions in the SUS316L, SUS316L-V and SUS316L-Zr steels.9)

Chemical composition (mass%)

C Si Mn P S Cr Ni Mo Al N O Additive

SUS316L 0.003 0.01 1.65 0.002 0.003 17.7 13.9 2.2 0.017 0.0020 0.00131 ®

SUS316L-V 0.004 <0.01 1.66 0.003 0.003 16.9 13.9 2.2 ® 0.0018 0.0187 0.28V

[image:2.595.46.290.408.480.2]

SUS316L-Zr 0.003 <0.01 1.64 0.002 0.003 16.7 13.9 2.3 0.027 0.0079 0.0067 0.78Zr

Table 2 Electron irradiation conditions in the SUS316L, SUS316L-V and SUS316L-Zr steels.

Material

Irradiation temperature

(T/K)

Irradiation dose (dpa)

Irradiation dose rate

(dpa/s)

SUS316L 723 7.2 2.0©10¹3

SUS316L-V 723 7.2 2.0©10¹3

SUS316L-Zr 723 14.4 2.0©10¹3

GB

100nm

DLFZ VDZ

VDZ VDZ

0.1 dpa 1.0 dpa 3.6 dpa 7.2 dpa

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irradiation dose so that DLFZ would be formed. On the other hand, when the excess vacancy concentration reaches that of void nucleation, voids are homogeneously nucleated as reported by Singh et al.13) However, vacancies induced near the GB also diffuse toward the GB so that vacancy concentration near the GB can be decreased. Then, voids could not be nucleated and the VDZ was formed near the GB. Actually, voids were homogeneously distributed in the area away from the GB and were regularly arranged along the GB, and also the VDZ was formed with a given width (Fig. 1).

Beyond the irradiation dose of 1.0 dpa, the void number density in the area away from the GB tended to increase and some voids seemed to be partially coalesced during irradiation to 7.2 dpa. These results suggested that the point defect accumulation behavior could reach the steady-state at 7.2 dpa so that VDZ widths would not change even at higher doses as reported by Konobeev et al.14) The similar behavior for VDZ formations was observed during electron irradiations in other steels as shown in Fig. 2.

3.2 Voids distributions and VDZ widths

Figure 2 shows typical microstructures observed near GBs in the SUS316L and the modified SUS316L steels after electron irradiation at 723 K. For the SUS316L and SUS316L-V steels, voids were homogeneously observed in the area away from the GBs after irradiation to 7.2 dpa (Figs. 2(a) and 2(b)). The mean void size in the SUS316L-V steel was somewhat smaller than that in the SUS316L steel. This would be due to the reduction of the void growth rate by the interaction between vacancies and V elements. Figure 2(c) shows the void distribution in the SUS316L-Zr steel after irradiation to 14.4 dpa. Smaller voids with higher density in comparison with other two steels were formed in the area away from the GB. This was because Zr interacted more strongly with vacancies than V did, thus the coupling sites of Zr atoms and vacancies would act as void nucleation sites. These results also suggested that addition of oversized elements like V or Zr caused the reduction of vacancy mobility corresponding to vacancy diffusivity or flux as indicated by Kato et al.9) Namely, the mobility reduction means that the mean free path of the vacancies would be reduced by the strong interaction between oversized minor elements and vacancies. Furthermore, the effects of the

interaction would be different depending on the sorts of added elements. Especially the Zr addition would be more effective than V addition to reduce vacancy mobility due to the size effect for vacancy trapping.9,10)

Then, the effects of the interaction among the additional elements and vacancies were studied by focusing on voids nucleation and growth near GBs. The zones without void formation (VDZs) were observed with a given width along GBs in both the SUS316L and SUS316L-V steels (Figs. 2(a) and 2(b)). The VDZ widths in the SUS316L and SUS316L-V steels were about 119 nm and about 100 nm, respectively. On the other hand, the VDZ formation was also recognized in the SUS316L-Zr steel, but it was difficult to estimate the VDZ width exactly in the present study because voids were regularly distributed in the extremely narrow region along the GB (Fig. 2(c)). From these results, the reduction of vacancy diffusivity andflux by additions of V or Zr elements would be reflected on the decrease of VDZ widths. Namely, the excess irradiation-induced vacancies would be less likely to flow toward the GB due to the reduction of vacancy mobility by the addition of minor elements so that vacancy flux to the GBs would decrease. As a result, VDZ widths would become narrow in alloys with additional minor elements.

Kato et al.9) estimated vacancy migration energy in the SUS316L-V steel as 1.6©10¹19J (1.0 eV) and this value was not significantly different from the energy in SUS316L steel of 1.71©10¹19J (1.07 eV). Thus, the difference in vacancy mobility among these steels cannot be explained based on the vacancy migration energy. So it is necessary to estimate the vacancy migration energy for the SUS316L and SUS316L-V steels more precisely. However the void swelling was surely decreased due to the addition of V element.9)In addition, the reduction of void growth rate by addition of V element was also confirmed in this study. Therefore, the vacancy trapping effect by V element must cause the reduction of vacancy mobility. On the other hand, in the SUS316L-Zr steel, Shigenaka et al.18) estimated the vacancy migration energy as about 3.0©10¹19J (1.9 eV). The binding energy between Zr atoms and vacancies was clearly higher in comparison with that between V atoms and vacancies. This means that Zr addition decreases the vacancy mobility more than V addition. This is why the VDZ width in the SUS316L-Zr steel was extremely narrow.

Materials (a) SUS316L (b) SUS316L-V (c) SUS316L-Zr

TEM images

VDZ widths 119 ± 13 nm 100 ± 19 nm Not clearly observed 100nm

GB

VDZ

100nm

100nm

void

50nm

[image:3.595.72.524.71.219.2]
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3.3 Analysis of parameters related to vacancy accumu-lation behavior

As described in Section 3.2, the VDZs were clearly observed in the SUS316L and SUS316L-V steels and the widths were different depending on the steels. Konobeev

et al.14)and Sakaguchiet al.16) showed that the VDZ width and DLFZ width can be theoretically estimated according to eqs. (1) and (2).

w¼ ½Dv=4K®R1=4 ð1Þ

rgb

c ¼ ½2DiCi=Gdpa1=2 ð2Þ Here, in eq. (1), w is the VDZ width, Dv is the vacancy diffusivity, K is the irradiation dose rate and ®R is the recombination coefficient which is independent of temper-ature. In eq. (2),rgb

c is the critical capture radius of GBs for SIAs,DiCiis theflux of the SIAs andGdpais the irradiation dose rate. The assumption was made that the critical capture radius, rgb

c in eq. (2), could also be applied for vacancies, thenrgb

c corresponded to VDZ widthw. Furthermore, at the steady-state, DiCi was assumed to be almost equal to DvCv (vacancy flux). Therefore, the ratio of vacancy diffusivity in the SUS316L-V steel to that in the SUS316L steel and the ratio offlux in the SUS316L-V steel to that in the SUS316L steel could be estimated from eqs. (1) and (2) and the experimentally-obtained VDZ width.

When it was assumed that ®Rin eq. (1) was not changed significantly among the SUS316L and SUS316L-V steels, the ratio for w could be expressed as eq. (3) using eq. (1) becauseKandTwere also constant in the present experiment.

wSUS316L-V=wSUS316L¼ ½Dv,SUS316L-V=Dv,SUS316L1=4 ð3Þ Equation (3) indicates that the ratio for the VDZ width can be expressed as a function of the ratio for vacancy diffusivity. Therefore, from the experimentally-obtained VDZ widths of 119 nm in the SUS316L steel and 100 nm in the SUS316L-V steel, the ratio of the vacancy diffusivity in the SUS316L-V steel to that in the SUS316L steel could be estimated as 0.50. This means that vacancy diffusivity was decreased due to the interaction of vacancies with addition of V.

On the other hand, when vacancyflux was considered, the ratio for rgb

c (=w) among the SUS316L and SUS316L-V steels could be expressed from eq. (2) as shown in eq. (4).

wSUS316L-V=wSUS316L

¼ ½DvCv,SUS316L-V=DvCv,SUS316L1=2 ð4Þ Thus, the ratio of the vacancyflux in the SUS316L-V steel to that in the SUS316L steel could be estimated as 0.71 using the experimentally-obtained VDZ widths. Namely, it was evaluated that the vacancy flux flowing toward GB in SUS316L-V steel was lower than that in the SUS316L steel. Moreover, the equation of the ratio for the vacancy flux was expressed by the components of the ratio for the vacancy diffusivity and the ratio for excess vacancy concentration as shown in eq. (5).

DvCv,SUS316L-V=DvCv,SUS316L

¼ ½Dv,SUS316L-V=Dv,SUS316L½Cv,SUS316L-V=Cv,SUS316L ð5Þ The ratios for vacancy diffusivity and flux between the SUS316L and SUS316L-V steels were 0.50 and 0.71, respectively. By substituting these values into eq. (5), the

ratio for the excess vacancy concentration was estimated as 1.41. These results mean that the excess vacancy concen-tration in the matrix for the SUS316L steel containing V elements was higher than that in the SUS316L steel without additional elements. This would be attributed to the number of vacancies which were absorbed at sinks (i.e., dislocations) being decreased as a result of the trapping effect due to the interaction between vacancies and V elements. Thus, the addition of minor elements which preferentially interact with vacancies would cause the decreasing vacancy diffusivity and

flux, while the excess vacancy concentration would be increased. The vacancy trapping effect by V element could be directly reflected onto the estimated ratios for the present study parameters.

In this study, it was not possible to measure the VDZ width and estimate the ratios for vacancy accumulation behavior in the SUS316L-Zr. However, if the VDZ width in the SUS316L-Zr steel has a finite value, which may be a few nanometers, the ratios of vacancy diffusivity and flux in the SUS316L-Zr steel to those in the SUS316L steel would be decreased more and the ratio of the excess vacancy concentration would be enhanced more compared to the ratios between the SUS316L-V and SUS316L steels.

From the above considerations, it was expected that comparative evaluations of vacancy diffusivity and flux between a base alloy and modified alloys with specific additives would be possible from the analysis of experimen-tally obtained VDZ widths. Also, the excess vacancy concentration could be evaluated. The evaluations would be effective to evaluate the effect of additional minor elements on void swelling behavior because the void swelling rates and the incubation period can be closely attributed to these parameters. Actually, for type 316 steels including the present steels, it has been indicated by Katoet al.9)that void swelling rates were decreased and the incubation periods were prolonged by addition of minor elements; especially Zr addition to SUS316L steel had a strong suppression effect on void swelling. In this study, it was actually confirmed that Zr addition decreased the parameters such as vacancy diffusivity and flux from analyses of the VDZ width. Therefore, even though it is also necessary to consider the combined effects with interstitial impurities, the evaluations of these void swelling-related parameters from analyses of VDZ widths will be reflected onto future alloying design specifications such as the determination of suitable minor elements to suppress void swelling.

4. Conclusion

In order to perform the comparative evaluations for vacancy diffusivity and flux between a base alloy and modified alloys, the VDZ widths were experimentally measured from the TEMin-situ observation during electron irradiation of SUS316L, SUS316L-V and SUS316L-Zr steels at 723 K. The results are summarized as follows.

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(3) From the analyses of measured VDZ widths in the SUS316L and SUS316L-V steels, the changes of vacancy diffusivity, vacancy flux and excess vacancy concentration were evaluated, and their ratios were 0.50, 0.71 and 1.41, respectively. The decreases of vacancy diffusivity andflux during electron irradiation would be due to the interaction of vacancies with added minor elements, while the enhancement of the excess vacancy concentration would be caused as a result of the trapping effect due to alloying elements.

Acknowledgment

This work was supported by Grant-in-Aid for Scientific Research (KAKENHI, 23561024) from the Japan Society for the Promotion of Science (JSPS).

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Figure

Table 1Chemical compositions in the SUS316L, SUS316L-V and SUS316L-Zr steels.9)
Fig. 2TEM images and VDZ widths. Void distributions near the random GB after electron irradiation at 723 K to 7.2 dpa for: (a) theSUS316L steel and (b) the SUS316L-V steel

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