Effect of grain boundary on the cavity formation behavior in 1.4 MeV Ar⁺ irradiated 18Cr10NiTi-ODS steel
The formation of cavity denuded zones (DZ) near grain boundary (GB) in 18Cr10NiTi-ODS steel with the addition of Y₂O₃-ZrO₂ nano-oxides irradiated with energetic Ar-ions in the dose range of 40…110 displacements per atom (dpa) with simultaneously implanted argon to the levels of 0.08…7 at.% at temper...
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Національний науковий центр «Харківський фізико-технічний інститут» НАН України
2023
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| Cite this: | Effect of grain boundary on the cavity formation behavior in 1.4 MeV Ar⁺ irradiated 18Cr10NiTi-ODS steel / G.D. Tolstolutskaya, S.A. Karpov, A.S. Kalchenko, M.A. Tikhonovsky // Problems of Atomic Science and Technology. — 2023. — № 2. — С. 15-20. — Бібліогр.: 26 назв. — англ. |
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Tolstolutskaya, G.D. Karpov, S.A. Kalchenko, A.S. Tikhonovsky, M.A. 2023-12-10T12:45:10Z 2023-12-10T12:45:10Z 2023 Effect of grain boundary on the cavity formation behavior in 1.4 MeV Ar⁺ irradiated 18Cr10NiTi-ODS steel / G.D. Tolstolutskaya, S.A. Karpov, A.S. Kalchenko, M.A. Tikhonovsky // Problems of Atomic Science and Technology. — 2023. — № 2. — С. 15-20. — Бібліогр.: 26 назв. — англ. 1562-6016 PACS: 61.80.-X, 81.40.CD DOI: https://doi.org/10.46813/2023-144-015 https://nasplib.isofts.kiev.ua/handle/123456789/196092 The formation of cavity denuded zones (DZ) near grain boundary (GB) in 18Cr10NiTi-ODS steel with the addition of Y₂O₃-ZrO₂ nano-oxides irradiated with energetic Ar-ions in the dose range of 40…110 displacements per atom (dpa) with simultaneously implanted argon to the levels of 0.08…7 at.% at temperatures of 550…650 ℃ was investigated. Transmission electron microscopy has been used to study the microstructure evolution and width of cavity-denuded zones. Denuded zones are found to be dependent of the irradiation conditions, such as irradiation dose, dose rate and temperature. The impact of grain refinement and nanosized oxide precipitates on the characteristics of DZ are examined. Досліджено формування денудованих від порожнин зон поблизу меж зерен у сталі Х18Н10Т-ДЗО з додаванням нанооксидів Y₂O₃-ZrO₂, опроміненої високоенергетичними іонами Ar у діапазоні доз 40…110 зсувів на атом з одночасною імплантацією аргону до рівнів 0,08…7 ат.% при температурах 550…650 ℃. Трансмісійна електронна мікроскопія була використана для вивчення еволюції мікроструктури та ширини денудованих зон. Виявлено, що ширина денудованих зон залежить від умов опромінення, таких як доза опромінення, швидкість створення зсувів і температура. Вивчено вплив подрібнення зерна і нанорозмірних оксидних преципітатів на характеристики денудованих зон. The work was financially supported by the National Academy of Science of Ukraine (program “Fundamental scientific research on the most important problems of the development of scientific and technical, socio-economic, socio-political, human potential to ensure Ukraine's competitiveness in the world and sustainable development of society and the state”) and the European Federation of Academies of Sciences and Humanities (ALLEA), within the framework the “European Fund for Displaced Scientists”, Grant EFDSFL2-04. en Національний науковий центр «Харківський фізико-технічний інститут» НАН України Problems of Atomic Science and Technology Physics of radiation damages and effects in solids Effect of grain boundary on the cavity formation behavior in 1.4 MeV Ar⁺ irradiated 18Cr10NiTi-ODS steel Вплив границі зерна на характер утворення порожнин у сталі Х18Н10Т ДЗО, що опромінена іонами Ar⁺ з енергією 1,4 МеВ Article published earlier |
| institution |
Digital Library of Periodicals of National Academy of Sciences of Ukraine |
| collection |
DSpace DC |
| title |
Effect of grain boundary on the cavity formation behavior in 1.4 MeV Ar⁺ irradiated 18Cr10NiTi-ODS steel |
| spellingShingle |
Effect of grain boundary on the cavity formation behavior in 1.4 MeV Ar⁺ irradiated 18Cr10NiTi-ODS steel Tolstolutskaya, G.D. Karpov, S.A. Kalchenko, A.S. Tikhonovsky, M.A. Physics of radiation damages and effects in solids |
| title_short |
Effect of grain boundary on the cavity formation behavior in 1.4 MeV Ar⁺ irradiated 18Cr10NiTi-ODS steel |
| title_full |
Effect of grain boundary on the cavity formation behavior in 1.4 MeV Ar⁺ irradiated 18Cr10NiTi-ODS steel |
| title_fullStr |
Effect of grain boundary on the cavity formation behavior in 1.4 MeV Ar⁺ irradiated 18Cr10NiTi-ODS steel |
| title_full_unstemmed |
Effect of grain boundary on the cavity formation behavior in 1.4 MeV Ar⁺ irradiated 18Cr10NiTi-ODS steel |
| title_sort |
effect of grain boundary on the cavity formation behavior in 1.4 mev ar⁺ irradiated 18cr10niti-ods steel |
| author |
Tolstolutskaya, G.D. Karpov, S.A. Kalchenko, A.S. Tikhonovsky, M.A. |
| author_facet |
Tolstolutskaya, G.D. Karpov, S.A. Kalchenko, A.S. Tikhonovsky, M.A. |
| topic |
Physics of radiation damages and effects in solids |
| topic_facet |
Physics of radiation damages and effects in solids |
| publishDate |
2023 |
| language |
English |
| container_title |
Problems of Atomic Science and Technology |
| publisher |
Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
| format |
Article |
| title_alt |
Вплив границі зерна на характер утворення порожнин у сталі Х18Н10Т ДЗО, що опромінена іонами Ar⁺ з енергією 1,4 МеВ |
| description |
The formation of cavity denuded zones (DZ) near grain boundary (GB) in 18Cr10NiTi-ODS steel with the addition of Y₂O₃-ZrO₂ nano-oxides irradiated with energetic Ar-ions in the dose range of 40…110 displacements per atom (dpa) with simultaneously implanted argon to the levels of 0.08…7 at.% at temperatures of 550…650 ℃ was investigated. Transmission electron microscopy has been used to study the microstructure evolution and width of cavity-denuded zones. Denuded zones are found to be dependent of the irradiation conditions, such as irradiation dose, dose rate and temperature. The impact of grain refinement and nanosized oxide precipitates on the characteristics of DZ are examined.
Досліджено формування денудованих від порожнин зон поблизу меж зерен у сталі Х18Н10Т-ДЗО з додаванням нанооксидів Y₂O₃-ZrO₂, опроміненої високоенергетичними іонами Ar у діапазоні доз 40…110 зсувів на атом з одночасною імплантацією аргону до рівнів 0,08…7 ат.% при температурах 550…650 ℃. Трансмісійна електронна мікроскопія була використана для вивчення еволюції мікроструктури та ширини денудованих зон. Виявлено, що ширина денудованих зон залежить від умов опромінення, таких як доза опромінення, швидкість створення зсувів і температура. Вивчено вплив подрібнення зерна і нанорозмірних оксидних преципітатів на характеристики денудованих зон.
|
| issn |
1562-6016 |
| url |
https://nasplib.isofts.kiev.ua/handle/123456789/196092 |
| citation_txt |
Effect of grain boundary on the cavity formation behavior in 1.4 MeV Ar⁺ irradiated 18Cr10NiTi-ODS steel / G.D. Tolstolutskaya, S.A. Karpov, A.S. Kalchenko, M.A. Tikhonovsky // Problems of Atomic Science and Technology. — 2023. — № 2. — С. 15-20. — Бібліогр.: 26 назв. — англ. |
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2025-11-26T20:39:34Z |
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2025-11-26T20:39:34Z |
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| fulltext |
ISSN 1562-6016. Problems of Atomic Science and Technology. 2023. №2(144) 15
https://doi.org/10.46813/2023-144-015
EFFECT OF GRAIN BOUNDARY ON THE CAVITY FORMATION
BEHAVIOR IN 1.4 MeV Ar
+
IRRADIATED 18Cr10NiTi-ODS STEEL
G.D. Tolstolutskaya, S.A. Karpov, A.S. Kalchenko, M.A. Tikhonovsky
National Science Center “Kharkov Institute of Physics and Technology”, Kharkіv, Ukraine
E-mail: g.d.t@kipt.kharkov.ua
The formation of cavity denuded zones (DZ) near grain boundary (GB) in 18Cr10NiTi-ODS steel with the
addition of Y2O3-ZrO2 nano-oxides irradiated with energetic Ar-ions in the dose range of 40…110 displacements
per atom (dpa) with simultaneously implanted argon to the levels of 0.08…7 at.% at temperatures of 550…650 ºC
was investigated. Transmission electron microscopy has been used to study the microstructure evolution and width
of cavity-denuded zones. Denuded zones are found to be dependent of the irradiation conditions, such as irradiation
dose, dose rate and temperature. The impact of grain refinement and nanosized oxide precipitates on the
characteristics of DZ are examined.
PACS: 61.80.-X, 81.40.CD
INTRODUCTION
Various approaches are being explored to improve
the irradiation tolerance of metals, including the
introduction of high densities of grain boundaries
(GBs), interphase boundaries, or free surfaces. [1, 2].
These boundaries act as sinks for point defects, making
them efficient in enhancing the material's resistance to
irradiation. Recent studies suggest that nanocrystalline
metals with a large specific area of grain boundaries
exhibit better irradiation resistance compared to their
coarse-grained equivalents, thereby offering a promising
way for enhancing the irradiation resistance of many
materials [3].
Radiation swelling remains a significant issue for
nuclear reactor core parts, along with other radiation-
related concerns such as transmutation doping of
materials with inert gas atoms (such as helium) that
cause degradation of the mechanical properties of
reactor materials through high-temperature
embrittlement, fatigue, creep, and gas swelling.
Noble gas atoms in solids typically have a tendency
to form bonds with vacancy-type defects. This prevents
the vacancies created by neutron irradiation from
recombining with self-interstitial atoms, causing them to
accumulate and form complexes with gas atoms.
Interactions between helium-vacancy complexes and
thermal vacancies lead to the development of gas
porosity (GP) in structural materials at high operating
temperatures. During their growth, gas bubbles tend to
accumulate at grain boundaries, leading to severe
deterioration of materials [4]. On the other hand, both
gas bubbles and pores can also contribute to the
formation of denuded zones (DZ) near GB, interphase
boundaries, or free surfaces. The formation of a DZ can
be used to understand how inert gases affect the sink-
defect absorption efficiency of different types of
boundaries.
To study the effects of high levels of helium and
displacement damage, dual ion beam irradiations are
often used [5]. Alternative approach is to use heavier
noble gases with a larger atomic mass than helium, such
as high-energy argon ions, which can effectively create
high-level displacement damage and simulate helium
effects since the behavior of Ar atoms is thought to be
similar to that of He in irradiated metals [6, 7].
The 18Cr10NiTi-ODS steel was found to have the
considerable swelling resistance under Ar
+
irradiation
[8]. The presence of fine-grained structures with high
boundary area and finely distributed dispersoids in this
steel enhance the stability of the grain structure and
provide defect trapping and annihilation sites, resulting
in improved irradiation resistance upon Ar
+
irradiation.
The purpose of this study is to reveal the features of
cavity DZ formation during 1.4 MeV Ar irradiation of
18Cr10NiTi-ODS steel with added Y2O3-ZrO2 nano-
oxides in terms of the influence of inert gas, grain
refinement, nanosized oxide precipitates and irradiation
conditions, such as irradiation dose, dose rate and
temperature.
1. MATERIAL AND METHODS
The ODS steel used in this study is an austenitic
stain – less steel strengthened by Y2O3-ZrO2 nano-
oxides which was previously fabricated in NSC KIPT.
A detailed technological procedure of production is
described in [9]. Grain structure of ODS steel (Fig. 1)
was approximately the same for all samples, the average
grain size was 1.2…2.0 μm.
Fig. 1. Pre-irradiation microstructure
of 18Cr10NiTi-ODS steel
Significant concentration of precipitates and its near-
uniform distribution are observed for all samples.
Precipitations size varied from several to hundreds of
nanometers, but the last were a few orders less, thus, its
contribution to concentration and average size was
negligible. The average size of nano-precipitates is
estimated at ∼ 10 nm and their average density is
∼ 7.3 ·10
21
m
−3
.
mailto:g.d.t@kipt.kharkov.ua
16 ISSN 1562-6016. Problems of Atomic Science and Technology. 2023. №2(144)
The accelerating-measuring system “ESU-2” with a
residual target-chamber pressure of ~ 5∙10
-5
Pa was used
for the creation of radiation damage [10]. The argon
ions with energy of 1.4 MeV were chosen for irradiation
experiments. The irradiation temperature varied from
550 to 650 ºC. The error in the temperature
measurement did not exceed ± 5%. The error in the
beam current and, consequently of the damage dose, did
not exceed ± 10%.
Calculated by SRIM 2008 [11] depth distribution
profiles of damage and concentration of Ar atoms
implanted in 18Cr10NiTi steel to a dose of 1·10
17
cm
-2
are shown in Fig. 2. The damage calculations are based
on the Kinchin-Pease model (KP), with a displacement
energy for each alloying elements was set to 40 eV, as
recommended in ASTM E521-96 (2009) [12].
Fig. 2. The depth distribution of damage and Ar atoms
concentration calculated with SRIM for 18Cr10NiTi
steel irradiated with 1.4 MeV Ar ions to a dose
of 1·10
17
cm
-2
The changes of microstructure as a function of depth
are obtained in 100 nm sections from 0 to 800 nm (see
Fig. 2). The removing of ~ 100 nm depth-layer of
material was performed by the electro-pulse technique.
Microstructural and cavity-denuded zone data were
extracted using conventional techniques conducted on
JEM-100CX and JEM-2100 transmission electron
microscopes, employing standard bright-field
techniques.
2. RESULTS AND DISCUSSION
In a previous study, we examined the effects of
1.4 MeV Ar
+
irradiation on the microstructure evolution
and swelling behavior of austenitic steel 18Cr10NiTi at
temperatures ranging from 550 to 700 ºC [6]. The doses
used in the study ranged from 40 to 105 dpa, while the
levels of simultaneously implanted argon were between
0.08 and 6.3 at.%. Our findings demonstrated that the
microstructure changes induced by irradiation were
highly dependent on Ar concentration, implantation
temperature and level of displacements per atom.
The present study is focused on the relationship
between the development of DZ and the damage dose
and implanted argon concentration. Fig. 3 shows that a
large number of round-shaped cavities (no obvious
facets) with sizes of 1…8 nm was formed after
irradiation at 625 ºC, which is the temperature of
maximum swelling for this steel under Ar
+
irradiation
[6]. It can be seen that the cavity size distribution
correlates with the calculated profiles in Fig. 2: the
higher dose and concentration of argon, the larger the
cavities.
Although a large number of cavities were produced
at depth 0…100 nm, there is no obvious formation of
DZs around GBs, nor did we observe any defect-
denuded zones at GBs at depth 100…200 nm even
though the damage and concentration of argon have
increased.
a b c
Fig. 3. Microstructure of
18Cr10NiTi-ODS steel at specified
depths after Ar
+
irradiation at
625 °C: a – 0…100 nm;
b – 100…200 nm; c – 300…400 nm;
d – 500…600 nm; e – 700…800 nm
d e
ISSN 1562-6016. Problems of Atomic Science and Technology. 2023. №2(144) 17
Denudation of grain boundaries is most clearly
observed at depths starting at 200 nm, where the argon
concentration exceeds 0.4 at.% and the damage dose
exceeds 50 dpa. The observed trend agrees well
(correlates) with the evolution of cavity diameter,
density and swelling with depth in 18Cr10NiTi-ODS
steel irradiated with argon ions at the equivalent doses.
Cavity size and swelling increase with depth up to the
dpa peak region (400…500 nm depth) and then decrease
beyond the Ar implantation peak region [13, 14]. It is
noteworthy that in almost all cases the cavity size was
larger at the GBs than in the grain interiors.
To quantify the width of the DZ, we draw a line
along the GB and move it perpendicular to the GB plane
towards the grain interior until it intersected with a
visible bubble. The distance between the GB and this
line was considered as the DZ width (see Fig 3). The
measured DZ width was found to be in the range of
~ 17…25 nm for the entire interval of damage and the
dose rate at the temperature of 625 ºC.
A systematic and detailed study of the cavity
(including voids and bubbles, which are under-
pressurized cavities and over-pressurized cavities with
gas atoms, respectively) DZ near free surfaces and grain
boundaries in neutron- and ion-irradiated simple metals
(Cu, Ni, and Fe-Cr) was reported in [15]. It was shown
that the cavity DZ width, although gradually decreasing
with increasing depth (increasing dose rate), starts from
~ 700 nm. The DZ width values obtained in the current
study are much smaller. According to [15, 16], the
discrepancy observed can be explained by the dose rate
of irradiation, which influences the steady-state
concentration of vacancies. When the dose rate is
higher, the steady-state concentration of vacancies
increases, causing an increase in the concentration
gradient of vacancies for a given GB. As a result, a
region where the vacancy concentration is insufficient
for cavity formation will shift toward the GB, resulting
in a narrower DZ. The irradiation dose rate using
1.4 MeV Ar
+
ions was approximately 10
-2
dpa/s, which
was significantly higher than the 1.4·10
-3
dpa/s used in
reference [15]. This higher dose rate may lead to a
smaller DZ. In addition, when helium is introduced
through neutron transmutation or co-injection, DZ with
narrower widths than those of voids were observed.
This is probably due to the formation of He-vacancy
complexes, which have higher migration energy and
therefore result in a smaller cavity denuded zone width.
A similar trend can be seen in the case of argon
irradiation.
The formation of DZs is influenced by various
factors, such as the steady-state vacancy concentration,
diffusion temperature, and duration, as it is a diffusion-
controlled process [17]. Fig. 4 shows the effect of
irradiation temperature on microstructure of
18Cr10NiTi-ODS steel at depths 500…600 nm and
cavities denuded zone in the vicinity of grain boundaries
the after 1.4 MeV Ar
+
irradiation at 570…645 °C.
a b
c d
Fig. 4. Microstructure of 18Cr10NiTi-ODS steel at depths 500…600 nm after Ar
+
irradiation at 570 (a),
585 (b), 600 (c), and 645 °C (d)
18 ISSN 1562-6016. Problems of Atomic Science and Technology. 2023. №2(144)
In the present study, DZs were observed when Ar
ion irradiation was performed at temperatures above
570 °C. The measured DZ width was ~ 15…9 nm and
increased with increasing irradiation temperature,
indicating the influence of temperature. For a lower
irradiation temperature, the diffusivity of vacancies is
smaller, resulting in higher vacancy supersaturations
and hence smaller DZ widths. As temperature increases,
diffusivity of vacancies increases while supersaturation
decreases and the cavities DZ width increased from 15
to 39 nm at 570 and 645 °C, respectively.
While extensive research has been conducted on the
impact of GP in metals, and general patterns of GP
development based on damage rate, dose, and
irradiation temperature have been published [18, 19], it
is worth noting that each structural material exhibits its
own specific patterns.
The development of GP and the formation of DZ has
a more complicated character in 18Cr10NiTi-ODS steel
with its increased GB population and nano-sized oxide
precipitates compared to conventional 18Cr10NiTi steel
[8] (Fig. 5).
The numbers in Fig. 5 indicate the formation of
larger bubbles along the grain boundaries (1) and/or
dislocations (2). The formation of DZ near grain
boundaries (3) and no denuded grain boundaries was
observed (4). The heterogeneous distribution of bubbles
in size and density (5), the interaction of bubbles with
precipitates (6) the array of parallel chains of bubbles
(7) are also indicated.
Fig. 5. Inhomogeneous distribution of inert gas bubbles in X18H10T-ODS steels.
The numbers in the figure indicate the peculiarities of GP development in steel
A review of the literature revealed that the
experimental data could be classified into three distinct
categories: grains surrounded by fully denuded grain
boundaries (FDZ), grains surrounded by at least half
denuded grain boundaries (HDZ), and grains
surrounded by no denuded grain boundaries (NDZ).
Examples of such zones are shown in Fig. 5.
Grain boundaries or interfaces that have different
crystallography or composition exhibit notably different
structures and are therefore expected to demonstrate
varying sink efficiencies. Consequently, the widths of
zones denuded of vacancy clusters in close proximity to
different types of GBs may differ, suggesting a degree
of variation in GB sink/source efficiency [20–22].
Extensive research has been devoted to investigating
the correlation between DZ formation and GB
misorientation angle as well as grain size [23]. Results
have revealed that both low-angle and high-angle
boundaries can be denuded or non-denuded, and no
discernible trend linking DZ formation and size with
misorientation angle was observed. This suggests the
presence of an additional parameter that impacts GB
sink efficiency. Further research has demonstrated that
these processes are reliant on other factors beyond
misorientation angle, such as the GB plane [24].
Additionally, it has been demonstrated that DZ
formation is influenced not only by misorientation
angle, grain size, and GB type (high-angle or low-
angle), but also by other factors.
The analysis also revealed a highly non-uniform
distribution of gas bubbles throughout the grain volume.
Large bubbles formed only near GBs, in narrow zones
parallel to the boundaries. In contrast, small bubbles
with nearly identical diameters and high densities were
TB
ISSN 1562-6016. Problems of Atomic Science and Technology. 2023. №2(144) 19
present throughout the remainder of the internal grain
volume, far from dislocations. Moreover, some
coarsening of the bubbles also occurred near
dislocations.
Fig. 5 illustrates that certain bubbles are aligned in
chains (7) along previous dislocation lines, even though
there are no current dislocations present along these
chains. This observation indicates significant movement
of dislocations during irradiation. It is possible that the
bubbles collided with the dislocations and were
subsequently trapped by them, forming chains.
However, the dislocations then moved away, leaving the
entire chain in its original position.
Fig. 5 also shows that a large number of bubbles
were formed in the vicinity of the twin boundary (TB).
The distribution of these voids is roughly uniform and
there are no obvious DZs along the TB. This
observation is consistent with previous investigations on
irradiated Cu: defect agglomerates around the coherent
twin boundary are similar as those in the interior of
grains [24].
As can be seen from Fig. 5, the cavities are clustered
in proximity to the precipitates. The cavities started to
nucleate and grow at the interface between some oxide
particles and the matrix, indicating that the oxide/matrix
interface serves as a vacancy sink. The high concen-
tration of vacancies and inert gas atoms contributes to
the nucleation of cavities at the interface, which is in
agreement with previous observations in ODS
ferritic/martensitic steels [25] and ODS austenitic steels
[26]. In this case, denuded zones of small size are
observed.
CONCLUSIONS
The formation of denuded zones on GB in
18Cr10NiTi-ODS steel with the addition of Y2O3-ZrO2
nano-oxides irradiated with energetic Ar-ions in the
dose range of 40…110 dpa with simultaneously
implanted argon to the levels of 0.08…7 at.% at
temperatures of 550…650 ºC was investigated. The
results obtained in this study are summarized below.
Round cavities with sizes of 1…8 nm were formed
after irradiation. The cavity size distribution correlates
with the calculated damage and argon deposition
profiles: the higher the dose and argon concentration,
the larger the cavities.
Denudation of grain boundaries is observed at
depths beginning at 200 nm, where the argon
concentration exceeds 0.4 at.% and the damage dose
exceeds 50 dpa. DZ width ranges from 17 to 25 nm for
the entire range of damage and the dose rate at the
temperature of maximum swelling.
The cavity DZ width tends to increase with
increasing irradiation temperature.
Argon cavities DZ were found to be smaller
compared to the void DZ. This phenomenon is likely
due to the formation of Ar-vacancy complexes with
high migration energy.
The development of gas porosity and the formation
of DZs in 18Cr10NiTi-ODS steel has a complicated
character, which is attributed to its elevated GB
population and the presence of nanosized oxide
precipitates.
ACKNOWLEDGEMENTS
The work was financially supported by the National
Academy of Science of Ukraine (program
“Fundamental scientific research on the most important
problems of the development of scientific and technical,
socio-economic, socio-political, human potential to
ensure Ukraine's competitiveness in the world and
sustainable development of society and the state”) and
the European Federation of Academies of Sciences and
Humanities (ALLEA), within the framework the
“European Fund for Displaced Scientists”, Grant EFDS-
FL2-04.
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Article received 16.02.2023
ВПЛИВ ГРАНИЦІ ЗЕРНА НА ХАРАКТЕР УТВОРЕННЯ ПОРОЖНИН У СТАЛІ
Х18Н10Т ДЗО, ЩО ОПРОМІНЕНА ІОНАМИ Ar
+
З ЕНЕРГІЄЮ 1,4 МеВ
Г.Д. Толстолуцька, С.О. Карпов, О.С. Кальченко, М.А. Тихоновський
Досліджено формування денудованих від порожнин зон поблизу меж зерен у сталі Х18Н10Т-ДЗО з
додаванням нанооксидів Y2O3-ZrO2, опроміненої високоенергетичними іонами Ar у діапазоні доз
40…110 зсувів на атом з одночасною імплантацією аргону до рівнів 0,08…7 ат.% при температурах
550…650 ºC. Трансмісійна електронна мікроскопія була використана для вивчення еволюції мікроструктури
та ширини денудованих зон. Виявлено, що ширина денудованих зон залежить від умов опромінення, таких
як доза опромінення, швидкість створення зсувів і температура. Вивчено вплив подрібнення зерна і
нанорозмірних оксидних преципітатів на характеристики денудованих зон.
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