Тhe dose dependence of inert gases irradiation hardening of 316 austenitic stainless steel after low temperature irradiation
Irradiation-induced hardening has been investigated in relation to SS316 austenitic stainless steel. Samples were irradiated with 1400 keV/He and 1400 keV/Ar ions ions at fluences 0.01…10 displacements per atom (dpa) at room temperatures. Hardening of the surface layer was examined with nanoinde...
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Національний науковий центр «Харківський фізико-технічний інститут» НАН України
2018
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| Cite this: | Тhe dose dependence of inert gases irradiation hardening of 316 austenitic stainless steel after low temperature irradiation / S.A. Karpov, G.D. Tolstolutskaya, V.N. Voyevodin, G.N. Tolmachova, I.E. Kopanets // Вопросы атомной науки и техники. — 2018. — № 5. — С. 34-39. — Бібліогр.: 19 назв. — англ. |
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Digital Library of Periodicals of National Academy of Sciences of Ukraine| _version_ | 1859670065443504128 |
|---|---|
| author | Karpov, S.A. Tolstolutskaya, G.D. Voyevodin, V.N. Tolmachova, G.N. Kopanets, I.E. |
| author_facet | Karpov, S.A. Tolstolutskaya, G.D. Voyevodin, V.N. Tolmachova, G.N. Kopanets, I.E. |
| citation_txt | Тhe dose dependence of inert gases irradiation hardening of 316 austenitic stainless steel after low temperature irradiation / S.A. Karpov, G.D. Tolstolutskaya, V.N. Voyevodin, G.N. Tolmachova, I.E. Kopanets // Вопросы атомной науки и техники. — 2018. — № 5. — С. 34-39. — Бібліогр.: 19 назв. — англ. |
| collection | DSpace DC |
| container_title | Вопросы атомной науки и техники |
| description | Irradiation-induced hardening has been investigated in relation to SS316 austenitic stainless steel. Samples were
irradiated with 1400 keV/He and 1400 keV/Ar ions ions at fluences 0.01…10 displacements per atom (dpa) at room
temperatures. Hardening of the surface layer was examined with nanoindentation. The behavior of the hardnessdepth curve is analyzed with respect to the ion species. Regression analysis performed for hardening data using a
power-law function of the form ΔН ∞ (dpa)ⁿ
gives good agreement with the experimental data at n = 0.47 and 0.13
for low-dose and high-dose hardening, respectively. An applying of volume fraction analytical model showed the
possibility to simulate the hardness-depth behavior for ion-irradiated stainless steel with reasonable accuracy.
Вивчено радіаційно-індуковане зміцнення аустенітної нержавіючої сталі SS316. Зразки опромінювали
іонами 1400 кеВ/He і 1400 кеВ/Ar до доз 0,01…10 зсувів на атом (зна) при кімнатній температурі. Зміцнення
поверхневого шару досліджували методом наноіндентування. Проаналізовано поведінку кривої
твердістьглибина в залежності від сорту іонів. Регресійний аналіз, виконаний для даних по зміцненню з
використанням степеневої функції виду ΔН ∞ (зна)ⁿ, добре узгоджується з експериментальними даними при
n = 0,47 і 0,13 для низькодозного і високодозного режимів зміцнення відповідно. Застосування аналітичної
моделі об'ємної частки показало можливість з достатньою точністю моделювати поведінку твердості за
глибиної опроміненої нержавіючої сталі.
Изучено радиационно-индуцированное упрочнение аустенитной нержавеющей стали SS316. Образцы
облучали ионами 1400 кэВ/Не и 1400 кэВ/Ar до доз 0,01…10 смещений на атом (сна) при комнатной
температуре. Упрочнение поверхностного слоя исследовали методом наноиндентирования.
Проанализировано поведение кривой твердостьглубина в зависимости от сорта ионов. Регрессионный
анализ, выполненный для данных по упрочнению с использованием степенной функции вида ΔН ∞ (сна)ⁿ,
хорошо согласуется с экспериментальными данными при n = 0,47 и 0,13 для низкодозного и высокодозного
режимов упрочнения соответственно. Применение аналитической модели объемной доли показало
возможность с достаточной точностью моделировать поведение твердости по глубине облученной
нержавеющей стали.
|
| first_indexed | 2025-11-30T12:59:50Z |
| format | Article |
| fulltext |
34 ISSN 1562-6016. ВАНТ. 2018. №5(117)
UDC 669.017:539.16
THE DOSE DEPENDENCE OF INERT GASES IRRADIATION
HARDENING OF 316 AUSTENITIC STAINLESS STEEL AFTER LOW
TEMPERATURE IRRADIATION
S.A. Karpov, G.D. Tolstolutskaya, V.N. Voyevodin, G.N. Tolmachova, I.E. Kopanets
Institute of Solid State Physics, Material Science and Technology NSC KIPT,
Kharkov, Ukraine
E-mail: karpofff@kipt.kharkov.ua
Irradiation-induced hardening has been investigated in relation to SS316 austenitic stainless steel. Samples were
irradiated with 1400 keV/He and 1400 keV/Ar ions ions at fluences 0.01…10 displacements per atom (dpa) at room
temperatures. Hardening of the surface layer was examined with nanoindentation. The behavior of the hardness-
depth curve is analyzed with respect to the ion species. Regression analysis performed for hardening data using a
power-law function of the form Н (dpa)
n gives good agreement with the experimental data at n = 0.47 and 0.13
for low-dose and high-dose hardening, respectively. An applying of volume fraction analytical model showed the
possibility to simulate the hardness-depth behavior for ion-irradiated stainless steel with reasonable accuracy.
INTRODUCTION
Metals exposed to irradiation are known to harden
due to the generation of Frenkel pair defect clusters that
act as obstacles to dislocation motion under an applied
stress. This hardening increases the yield strength, y, of
the material but reduces the ductility and causes
embrittlement. Therefore characterizing the mechanical
properties and quantifying the changes observed in the
mechanical properties post irradiation is essential for the
safe design of nuclear reactors.
Irradiation hardening in metallic materials is strong
after irradiation at low temperatures (usually below
300 °C) because significant quantities of radiation-
induced defect clusters are retained, and they impede
the generation and glide of dislocations during
deformation [1].
The effects of high levels of helium under conditions
of simultaneous displacement damage production and
irradiation embrittlement are two of the most important
issues facing the development of steels for fusion
applications [2].
The 300 series austenitic stainless steels provide
high resistance to corrosion and oxidation and retain
high strength and excellent ductility over a temperature
range from cryogenic to elevated temperatures [3]. Such
favorable properties enable those steels to meet
requirements for application in nuclear facilities.
To simulate neutron irradiation damage of the
structural materials, heavy ion irradiation experiments
have been used because of the simplicity of use, easier
control of irradiation parameters, reduction of cost,
rapid damage production, the absence of induced
radioactivity, and the occurrence of the co-implantation
of helium/hydrogen.
On the other hand, ion irradiation has a significant
drawback – shallow depth of damage layer that making
it difficult to investigate the mechanical properties. The
solution of problem is possible by using
nanoindentation method that provides a study of the
mechanical properties of the samples in the near-surface
region. However, for the successful implementation of
this methodology, it is necessary to resolve such issues
as the correlation the change in strength with the plastic
deformation, the dose dependent of defect-cluster
accumulation and the damage gradient effect.
The aim of the present work is the determine the
dose dependent hardness from nanoindentation in heavy
ions irradiated SS316 steel and investigation of effects
of damage gradient and high levels of helium on the
hardening of SS316 steel.
1. MATERIAL AND METHODS
The specimens of SS316 steel with dimensions
1070.1 mm were used for investigations. Before
experiments the samples were annealed at 1340 K for
one hour in a vacuum ~10
-4
Pa. Chemical composition
of steel is shown in Tabl. 1.
Table 1
Chemical composition of SS316 steel, wt.%
С Si Mn P S Cr Ni Mo Fe
< 0.080 < 0.75 < 2.0 < 0.045 < 0.030 17.5 13.1 2.3 balanced
Samples were irradiated with 1.4 MeV argon ions to
a dose of 2.8·10
15
cm
-2
and 1.4 MeV helium ions to a
dose of 8·10
17
cm
-2
. All irradiations were carried out
with accelerating-measuring system “ESU-2” [4]. The
irradiation was performed at room temperature. Part of
each sample was masked from the ion beam, allowing
both an irradiated and unirradiated region of the sample
to be examined post irradiation.
Studies of the steel microstructure were performed
by transmission electron microscopy at room
temperature, employing standard bright-field techniques
on an EM-125 electron microscope at accelerating
voltage 125 kV. Preparation of specimens to suitable for
TEM thickness was performed using standard jet
electropolishing from unirradiated surface. The initial
structure of SS316 steel is shown in Fig. 1.
mailto:karpofff@kipt.kharkov.ua
ISSN 1562-6016. ВАНТ. 2018. №5(117) 35
Fig. 1. The initial microstructure of SS316 steel after
heat treatment at 1340 K/0.5 h
Nanohardness was measured by Nanoindenter
G200 with a Berkovich type indentation tip. Tests were
performed with a constant deformation rate of 0.05 s
-1
.
As a rule, ten measurements were performed every time
at a distance of 35 m from each other with subsequent
averaging of the results.
The methodology of Oliver and Pharr was used to
find the hardness [5]. The details of nanoindentation
tests have been presented elsewhere [6].
2. RESULTS AND DISCUSSION
In present paper we have determined values of
nanohardness of SS316 steel in the initial state and after
irradiation with 1.4 MeV helium or argon ions at Troom.
The depth distribution of gas atoms concentration
and damage for ion irradiation with helium and argon
ions shown in Fig. 2.
Ion stopping distribution for helium and argon ions
and irradiation damages (in dpa) in stainless steel have
been calculated with the software The Stopping and
Range of Ions in Matter (SRIM 2008) [7]. The dpa
calculations are based on a displacement energy
threshold of 40 eV and on the Kinchin-Pease formalism
and Stoller recommendations [8].
0.0 0.5 1.0 1.5 2.0 2.5 3.0
0
5
10
15
D
a
m
a
g
e
,
d
p
a
Depth, m
0
10
20
30
40
C
o
n
c
e
n
tr
a
ti
o
n
,
a
t.
%
0 200 400 600 800
0.0
0.5
1.0
1.5
2.0
D
a
m
a
g
e
,
d
p
a
Depth, nm
0.00
0.03
0.06
0.09
0.12
0.15
C
o
n
c
e
n
tr
a
ti
o
n
,
a
t.
%
a b
Fig. 2. Damages and concentrations profiles as a function of depth calculated using SRIM
for 1400 keV He
+
(a) and 1400 Ar
+
(b)
Hardness (H) as a function of indenter displacement
(h) is given in Fig. 3.
1
2
3
4
5
0 500 1000 1500 2000
Displacement, nm
H
a
rd
n
e
s
s
,
G
P
a
Ряд1
Ряд3
Ряд4
unirradiated
1400 keV He
+
1400 keV Ar
+
Fig. 3. Nanoindentation hardness of SS316 steel vs.
indentation depth of the unirradiated sample and
samples irradiated with He
+
and Ar
+
at Troom
In all samples, the first 100 nm of displacement
shows a considerable increase in the scatter of the data
due to tip-rounding artifacts [9] and surface preparation
effects. Therefore, for all samples the first 100 nm of
data will be ignored for the remainder of the analysis.
After the ion irradiation of specimens with He and
Ar ions at Troom an increase of nanohardness of about
two times is observed, independently of species of ions.
Indentation of ion irradiated materials will give
hardness that results from a superposition of the bulk
hardness, indentation size effect and the irradiation
induced hardening. The region of plastically deformed
material beneath the indentation penetrates significantly
deeper (Fig. 4) into the material than the displacement
of the indenter. Previous studies have shown that the
plastic zone can be approximated by a hemisphere with
a radius of 5…10 times the indentation depth [1].
Therefore, in an irradiated material with a shallow
damage depth, it is probable that part of the plastic zone
will extend in the underlying, unirradiated material.
With increasing of indentation depth, the measured
hardness will approach the hardness of unirradiated
material, since the part of unirradiated material within
the plastic zone increases.
In accordance with this consistency, peaks at 150
and 400 nm contact depth in the hardness profile (see
36 ISSN 1562-6016. ВАНТ. 2018. №5(117)
Fig. 3) corresponded to a SRIM calculated peaks at 500
and 2200 nm for argon and helium, respectively.
Fig. 4. Schematic of the indentation test.
The indentation-induced plastic zone is assumed
to be a hemisphere
The method of consideration of the soft substrate
effect for materials irradiated with accelerated ions was
first proposed by Kasada et al. in [10], where materials
of this kind were considered as system with coatings or
as “hardened layer–substrate” systems. The hardness of
the ion-irradiated region, according to Kasada, can be
determined by fitting the depth profile in the range of
100 nm < h < hc (hc is critical indentation depth) to the
Nix-Gao model [11].
By redrawing the experimental profiles of hardness
(see Fig. 3) in the coordinates “squared hardness–
reciprocal depth”, the bulk-equivalent hardness of the
ion-irradiated region has been evaluated from the
intercept of the linear fitting of data in the range of
100 nm < h < 400 nm for He-irradiated sample and in
the range of 100 nm < h < 150 nm for the Ar-irradiated
sample. The values of bulk-equivalent hardness were
found to be 4.2 and 3.8 GPa for helium and argon
irradiation, respectively.
2.1. THE DOSE DEPENDENCE
OF IRRADIATION HARDENING
Ref. [12] represents our previous results of study of
irradiation effect with 1.4 МeV argon ions within the
range of doses 0…10 dpa at 300 K on the hardening of
SS316 stainless steel. The hardness of the ion-irradiated
region of material has been determined according to
above mentioned approach of Kasada. It was discovered
that the nanohardness of the steel increases with the
damaging dose in the entire interval of radiation doses.
The sharpest effect is observed at low doses with a
gradual approach of the quasisaturation mode at high
fluencies.
It should be noted that G.S. Was et al. analyzing the
data of radiation induced segregation, irradiated
microstructure, radiation hardening and IASCC
susceptibility of the same heats of proton- and neutron-
irradiated 304SS and 316SS have shown that the
irradiation hardening of austenitic steels saturates at
about a few dpa [13].
A great deal of effort has been made to explain the
irradiation hardening behavior of metals, and to
correlate the change in strength with the number density
and size of radiation-induced defects and with
irradiation dose. Although there are multiple hypotheses
concerning the mechanisms of irradiation hardening
[14], the dose-dependence of the increase in yield stress,
ys, has been explored frequently using models based
on barrier hardening theory [15].
In the regression analysis [14], the radiation-induced
increase in yield stress, ys, was expressed in the form
of a power law: ys = h·(dpa)
n
, where h and n are the
regression coefficients and dpa is displacements per
atom. The log-log plots of ys vs. dpa data showed two
distinctive regimes: a low-dose regime where a rapid
hardening occurs and a high-dose regime where the log-
log plot shows a considerably reduced slope. Mean
values for n obtained from the 19 metals were about 0.5
for the low-dose regime and about 0.12 for the high-
dose regime.
The dose dependence of irradiation hardening in
SS316 irradiated with 1.4 MeV Ar ions is seen in Fig. 5.
The hardening data obtained in present study for helium
and argon irradiation are also included.
0.01 0.1 1 10
1
2
Ar-irradiation
He-irradiation
n=0.13
H
,
G
P
a
Damage, dpa
n=0.47
Fig. 5. Log-log plot for dose dependence of irradiation
hardening of 316 stainless steels
Approximation of hardness values by a power
function of the form Н (dpa)
n gives good agreement
with the experimental data at n = 0.47 and 0.13 for low-
dose and high-dose hardening, respectively.
In general n values were in the range 0.31…0.48 in
the low-dose regime and 0.01…0.24 in the high-dose
regime for the fcc metals; the average for the low-dose
regime, 0.4, was slightly lower than that for bcc metals,
0.55 [1]. Also, a trend band for 316 stainless steels
irradiated and tested at low temperatures ( 110 °C) was
obtained from the database for 316 stainless steels [16]
and shown that the n values for the database were 0.38
and 0.04 for the low-dose and high-dose regimes,
respectively.
2.2. THE VOLUME FRACTION MODEL
The values of bulk-equivalent hardness discussed in
previous paragraphs have been evaluated in accordance
with the methodology of Kasada et al. [10] from the
data fitting of the Nix-Gao plot. However, this method
did not take into account the damage gradient effect
(DGE). To extract irradiation induced hardening effect
precisely with a consideration of DGE, a rule-of-
mixtures type volume fraction approach has been used.
This method has recently been described in [1719].
In the framework of this approach, the hardness is a
volume-weighted average of the hardness of plastically
deformed material in the irradiated layer and the
unirradiated underlying substrate. Since the hardness
changes with the dose over the depth, the irradiated
ISSN 1562-6016. ВАНТ. 2018. №5(117) 37
layer can be divided into segments. Each segment is
assigned to its dose-dependent hardness for further
calculations of their individual contributions to the
overall hardness. The method allows to distinguish the
contribution of radiation hardening, ISE and substrate
hardness to the measured hardness.
The volume fraction model includes the following
assumptions:
1). The nanoindent is surrounded with a
hemispherical plastic zone beneath the surface. The
radius of hemisphere is larger than the indent depth by a
certain factor. This factor was fixed at 7 for simplicity.
It is assumed that the plastic zone increases linearly in
radius with indent depth.
2). The plastic zone is divided into a number of
segments with the same height h = 20 nm (see Fig. 4).
For each indent depth, the plastic zone extended from
the top surface to a certain depth, and each segment of
the plastic zone contributed to the overall hardness
measured at that indent depth. So that, for a maximum
indent of 2000 nm, the whole calculation depth would
be 14 m deep, and would contain 700 segments of
20 nm.
3). The volume of each segment is calculated for all
segments within the plastic zone as
22
2
2
1 33
6
hrr
h
V
, (1)
where r1
2
= r0
2
-z
2
, r2
2
= r0
2
-(z+h)
2
, r0
is the plastic zone
radius at the current indentation depth and z (increases
in increments of h depending on the segment number) is
the depth of the top of the segment from the surface (see
Fig. 4).
4). The radiation induced hardening of each segment
was calculated according to the simple power law
relationship as:
Hrad=m(D)
n
, (2)
where D is the dose in dpa and m and n are constants.
The dose at each depth was taken from the SRIM
calculations shown in Fig. 2.
5). According to volume fraction model, the
calculated radiation induced hardness at each indent
depth is the weighted average hardness of the segments
in the plastic zone:
)(
)()(
i
iirad
rad
V
VH
H , (3)
where Hrad(i) is the hardness value for segment i, and
V(i) is the volume of segment i.
To simulate contact depth hardness HC, we assume
that HC is a linear superposition of the hardness of the
unirradiated substrate HS and the irradiation-induced
hardness Hrad.
radSC HHH . (4)
The hardness of the unirradiated substrate HS
consists of the hardness due to the indentation size
effect, HISE, and the material hardness at an infinite
depth, H0.
0HHH ISES . (5)
Assuming that HISE and H0 are specific to the
material, these can be used in Equation (4) to model the
irradiated material. To obtain the Nix-Gao parameters
H0 and h* (a characteristic length), an approach [12]
have been applied to the unirradiated hardness data. The
values of 2.1 GPa and 190 nm were find for H0 and h*,
respectively.
The constants m and n are adjusted until agreement
is reached between the experimental and calculated
hardness vs. depth curves.
Fig. 6 shows the results of hardness-depth curve
simulations as well as experimental data for the cases of
argon and helium irradiation. The hardness Hrad
obtained from the volume fraction model is given as
dashed line. Parameters used in simulation are listed in
Tabl. 2.
Table 2
Simulation parameters
Irradiation conditions m n
Ar 1 0.2
He 1.5 0.2
0 500 1000 1500 2000
0
1
2
3
4
5
6
calculation
experiment
ISE
H
0
H
rad
H
a
rd
h
e
s
s
,
G
P
a
Depth, nm
0 500 1000 1500 2000 2500 3000
0
1
2
3
4
5
6
H
a
rd
n
e
s
s
,
G
P
a
Depth,nm
calculation
experiment
ISE
H
0
H
rad
a b
Fig. 6. Experimental hardness vs. displacement plot for 1.4 MeV Ar (o) (a) and 1.4 MeV He () (b). The bold solid
black and gray lines show the hardness obtained from the volume fraction model. The dotted lines show the material
hardness at an infinite depth H0; fine black lines HISE vs. indenter displacement.
The dashed lines show the irradiation-induced hardness Hrad vs. depth
38 ISSN 1562-6016. ВАНТ. 2018. №5(117)
It is seen that model exhibited good correlation, both
qualitatively and quantitatively, to the experimental
curves. The position, shape and calculated values of the
hardness-depth plot for Ar-irradiated sample are close
enough to the experimental results. For the case of He
irradiation, a slight discrepancy is observed in the
region of depths greater than 1500 nm. This may be
caused by the fact that at this depth the layer of
implanted helium ions arises (see Fig. 2) and reaches a
concentration over 30 at.% at a depth of 2.2 m. The
presence of helium in such quantities can affect the
hardness profile of irradiated steel.
It should also be noted that the value of the constant
n correlates with the value of the exponent of the power
function for the high-dose irradiation regime, which was
discussed in paragraph 2.1.
The hardness depth profile after ion irradiation
includes three different depth dependent effects: ISE,
DGE and effect of substrate. Irradiation with gaseous
(He, Ar) ions also should give additional effect in the
implanted layer – implanted-ion effect. Although this
effect is believed to be smaller than the effect of
irradiation hardening due to displacement damage, it
requires substantive consideration.
The data obtained in the present study indicate that a
significant loss of ductility of the austenitic steels of 300
series will be expected at fluences about 1…5 dpa
where the saturation of the density of the dislocation
loops is observed, and the accumulation of He/H
becomes significant.
CONCLUSIONS
Irradiation-hardening behaviors have been
investigated for SS316 austenitic stainless steel after
low-temperature (< 100 °C) irradiations. The following
conclusions were drawn:
The log-log plots of H vs. dpa data showed two
distinct regimes: a low-dose regime and a high-dose
regime. Regression analysis performed for those
regimes using a power-law function of the form
Н (dpa)
n gives good agreement with the
experimental data at p = 0.47 and 0.13 for low-dose and
high-dose hardening, respectively.
The simple volume fraction analytical model
demonstrated the ability to simulate the hardness-depth
behavior for ion-irradiated stainless steel with
reasonable accuracy. This allows to predict changes in
hardness at a specified level of radiation damage.
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Статья поступила в редакцию 31.08.2018 г.
ISSN 1562-6016. ВАНТ. 2018. №5(117) 39
ДОЗОВАЯ ЗАВИСИМОСТЬ УПРОЧНЕНИЯ 316 АУСТЕНИТНОЙ НЕРЖАВЕЮЩЕЙ
СТАЛИ ПРИ НИЗКОТЕМПЕРАТУРНОМ ОБЛУЧЕНИИ ИОНАМИ ИНЕРТНЫХ ГАЗОВ
С.А. Карпов, Г.Д. Толстолуцкая, В.Н. Воеводин, Г.Н. Толмачева, И.Е. Копанец
Изучено радиационно-индуцированное упрочнение аустенитной нержавеющей стали SS316. Образцы
облучали ионами 1400 кэВ/Не и 1400 кэВ/Ar до доз 0,01…10 смещений на атом (сна) при комнатной
температуре. Упрочнение поверхностного слоя исследовали методом наноиндентирования.
Проанализировано поведение кривой твердостьглубина в зависимости от сорта ионов. Регрессионный
анализ, выполненный для данных по упрочнению с использованием степенной функции вида Н (сна)
n
,
хорошо согласуется с экспериментальными данными при n = 0,47 и 0,13 для низкодозного и высокодозного
режимов упрочнения соответственно. Применение аналитической модели объемной доли показало
возможность с достаточной точностью моделировать поведение твердости по глубине облученной
нержавеющей стали.
ДОЗОВА ЗАЛЕЖНІСТЬ ЗМІЦНЕННЯ 316 АУСТЕНІТНОЇ НЕРЖАВІЮЧОЇ СТАЛІ
ПРИ НИЗЬКОТЕМПЕРАТУРНОМУ ОПРОМІНЕННІ ІОНАМИ ІНЕРТНИХ ГАЗІВ
С.О. Карпов, Г.Д. Толстолуцька, В.М. Воєводін, Г.М. Толмачова, І.Е. Копанець
Вивчено радіаційно-індуковане зміцнення аустенітної нержавіючої сталі SS316. Зразки опромінювали
іонами 1400 кеВ/He і 1400 кеВ/Ar до доз 0,01…10 зсувів на атом (зна) при кімнатній температурі. Зміцнення
поверхневого шару досліджували методом наноіндентування. Проаналізовано поведінку кривої
твердістьглибина в залежності від сорту іонів. Регресійний аналіз, виконаний для даних по зміцненню з
використанням степеневої функції виду Н (зна)
n
, добре узгоджується з експериментальними даними при
n = 0,47 і 0,13 для низькодозного і високодозного режимів зміцнення відповідно. Застосування аналітичної
моделі об'ємної частки показало можливість з достатньою точністю моделювати поведінку твердості за
глибиної опроміненої нержавіючої сталі.
|
| id | nasplib_isofts_kiev_ua-123456789-147698 |
| institution | Digital Library of Periodicals of National Academy of Sciences of Ukraine |
| issn | 1562-6016 |
| language | English |
| last_indexed | 2025-11-30T12:59:50Z |
| publishDate | 2018 |
| publisher | Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
| record_format | dspace |
| spelling | Karpov, S.A. Tolstolutskaya, G.D. Voyevodin, V.N. Tolmachova, G.N. Kopanets, I.E. 2019-02-15T17:56:44Z 2019-02-15T17:56:44Z 2018 Тhe dose dependence of inert gases irradiation hardening of 316 austenitic stainless steel after low temperature irradiation / S.A. Karpov, G.D. Tolstolutskaya, V.N. Voyevodin, G.N. Tolmachova, I.E. Kopanets // Вопросы атомной науки и техники. — 2018. — № 5. — С. 34-39. — Бібліогр.: 19 назв. — англ. 1562-6016 https://nasplib.isofts.kiev.ua/handle/123456789/147698 669.017:539.16 Irradiation-induced hardening has been investigated in relation to SS316 austenitic stainless steel. Samples were irradiated with 1400 keV/He and 1400 keV/Ar ions ions at fluences 0.01…10 displacements per atom (dpa) at room temperatures. Hardening of the surface layer was examined with nanoindentation. The behavior of the hardnessdepth curve is analyzed with respect to the ion species. Regression analysis performed for hardening data using a power-law function of the form ΔН ∞ (dpa)ⁿ gives good agreement with the experimental data at n = 0.47 and 0.13 for low-dose and high-dose hardening, respectively. An applying of volume fraction analytical model showed the possibility to simulate the hardness-depth behavior for ion-irradiated stainless steel with reasonable accuracy. Вивчено радіаційно-індуковане зміцнення аустенітної нержавіючої сталі SS316. Зразки опромінювали іонами 1400 кеВ/He і 1400 кеВ/Ar до доз 0,01…10 зсувів на атом (зна) при кімнатній температурі. Зміцнення поверхневого шару досліджували методом наноіндентування. Проаналізовано поведінку кривої твердістьглибина в залежності від сорту іонів. Регресійний аналіз, виконаний для даних по зміцненню з використанням степеневої функції виду ΔН ∞ (зна)ⁿ, добре узгоджується з експериментальними даними при n = 0,47 і 0,13 для низькодозного і високодозного режимів зміцнення відповідно. Застосування аналітичної моделі об'ємної частки показало можливість з достатньою точністю моделювати поведінку твердості за глибиної опроміненої нержавіючої сталі. Изучено радиационно-индуцированное упрочнение аустенитной нержавеющей стали SS316. Образцы облучали ионами 1400 кэВ/Не и 1400 кэВ/Ar до доз 0,01…10 смещений на атом (сна) при комнатной температуре. Упрочнение поверхностного слоя исследовали методом наноиндентирования. Проанализировано поведение кривой твердостьглубина в зависимости от сорта ионов. Регрессионный анализ, выполненный для данных по упрочнению с использованием степенной функции вида ΔН ∞ (сна)ⁿ, хорошо согласуется с экспериментальными данными при n = 0,47 и 0,13 для низкодозного и высокодозного режимов упрочнения соответственно. Применение аналитической модели объемной доли показало возможность с достаточной точностью моделировать поведение твердости по глубине облученной нержавеющей стали. en Національний науковий центр «Харківський фізико-технічний інститут» НАН України Вопросы атомной науки и техники Физика радиационных повреждений и явлений в твердых телах Тhe dose dependence of inert gases irradiation hardening of 316 austenitic stainless steel after low temperature irradiation Дозова залежність зміцнення 316 аустенітної нержавіючої сталі при низькотемпературному опроміненні іонами інертних газів Дозовая зависимость упрочнения 316 аустенитной нержавеющей стали при низкотемпературном облучении ионами инертных газов Article published earlier |
| spellingShingle | Тhe dose dependence of inert gases irradiation hardening of 316 austenitic stainless steel after low temperature irradiation Karpov, S.A. Tolstolutskaya, G.D. Voyevodin, V.N. Tolmachova, G.N. Kopanets, I.E. Физика радиационных повреждений и явлений в твердых телах |
| title | Тhe dose dependence of inert gases irradiation hardening of 316 austenitic stainless steel after low temperature irradiation |
| title_alt | Дозова залежність зміцнення 316 аустенітної нержавіючої сталі при низькотемпературному опроміненні іонами інертних газів Дозовая зависимость упрочнения 316 аустенитной нержавеющей стали при низкотемпературном облучении ионами инертных газов |
| title_full | Тhe dose dependence of inert gases irradiation hardening of 316 austenitic stainless steel after low temperature irradiation |
| title_fullStr | Тhe dose dependence of inert gases irradiation hardening of 316 austenitic stainless steel after low temperature irradiation |
| title_full_unstemmed | Тhe dose dependence of inert gases irradiation hardening of 316 austenitic stainless steel after low temperature irradiation |
| title_short | Тhe dose dependence of inert gases irradiation hardening of 316 austenitic stainless steel after low temperature irradiation |
| title_sort | тhe dose dependence of inert gases irradiation hardening of 316 austenitic stainless steel after low temperature irradiation |
| topic | Физика радиационных повреждений и явлений в твердых телах |
| topic_facet | Физика радиационных повреждений и явлений в твердых телах |
| url | https://nasplib.isofts.kiev.ua/handle/123456789/147698 |
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