Temperature dependence of surface topography and deuterium interaction with a pure α-Fe exposed to low-energy high-flux D plasma
Surface topography and deuterium interaction with a-Fe under glow discharge hydrogen (deuterium) ions bombardment with energy of ~1 keV at ion fluencies of (0.02…1)∙10²⁴ D/m² and various temperatures have been examined. The methods used were scanning electron microscopy, thermal desorption spectrosc...
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| Zitieren: | Temperature dependence of surface topography and deuterium interaction with a pure α-Fe exposed to low-energy high-flux D plasma / A.V. Nikitin, G.D. Tolstolutskaya, V.V. Ruzhytskiy, I.E. Kopanets, S.A. Karpov, R.L. Vasilenko, G.Y. Rostova, N.D. Rybalchenko // Вопросы атомной науки и техники. — 2016. — № 6. — С. 117-120. — Бібліогр.: 8 назв. — англ. |
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Nikitin, A.V. Tolstolutskaya, C.D. Ruzhytskiy, V.V. Kopanets, I.E. Karpov, S.A. Vasilenko, R.L. Rostova, G.Y. Rybalchenko, N.D. 2017-04-05T06:30:26Z 2017-04-05T06:30:26Z 2016 Temperature dependence of surface topography and deuterium interaction with a pure α-Fe exposed to low-energy high-flux D plasma / A.V. Nikitin, G.D. Tolstolutskaya, V.V. Ruzhytskiy, I.E. Kopanets, S.A. Karpov, R.L. Vasilenko, G.Y. Rostova, N.D. Rybalchenko // Вопросы атомной науки и техники. — 2016. — № 6. — С. 117-120. — Бібліогр.: 8 назв. — англ. 1562-6016 PACS: 61.72.Cc, 68.55.Ln https://nasplib.isofts.kiev.ua/handle/123456789/115453 Surface topography and deuterium interaction with a-Fe under glow discharge hydrogen (deuterium) ions bombardment with energy of ~1 keV at ion fluencies of (0.02…1)∙10²⁴ D/m² and various temperatures have been examined. The methods used were scanning electron microscopy, thermal desorption spectroscopy and the D(³He,p) ⁴He nuclear reaction. Formation of blisters was observed in the temperature range 230…340 K. Roundshaped cavities contained small nonmetallic particles FexOy (x=1…2, y=1…4) were founded on the irradiated surface of α-Fe. Temperature dependence of average blister diameter, the deuterium depth profile and temperature of deuterium retention were studied Изучена топография поверхности и взаимодействие дейтерия с a-Fe под воздействием тлеющего разряда ионов водорода (дейтерия) с энергией ~ 1 кэВ при ионных флюенсах (0,02…1)∙10²⁴ D/м² и различных температурах. Использовались методы сканирующей электронной микроскопии, термодесорбционной спектроскопии и ядерных реакций D(³He,p) ⁴He. В интервале температур 230…340 К наблюдалось образование блистеров. На облучённой поверхности -Fe были обнаружены полости округлой формы, содержащие небольшие неметаллические частицы FexOy (х=1…2, у=1…4). Обсуждаются: температурная зависимость среднего диаметра блистеров, распределение дейтерия по глубине образца и особенности удержания дейтерия. Вивчено топографію поверхні і взаємодію дейтерію з a-Fe під впливом тліючого розряду іонів водню (дейтерію) з енергією ~ 1 кеВ при іонних флюенсах (0,02…1)∙10²⁴ D/м² і різних температурах. Використовувалися методи скануючої електронної мікроскопії, термодесорбційної спектроскопії і ядерних реакцій D(³He,p) ⁴He. В інтервалі температур 230…340 К спостерігалось утворення блістерів. На опроміненій поверхні -Fe були виявлені порожнини округлої форми, що містять невеликі неметалічні частки FexOy (х=1…2, у=1…4). Обговорюються: температурна залежність середнього діаметра блістерів, розподіл дейтерію по глибині зразка і особливості утримання дейтерію. en Національний науковий центр «Харківський фізико-технічний інститут» НАН України Вопросы атомной науки и техники Plasma dynamics and plasma-wall interaction Temperature dependence of surface topography and deuterium interaction with a pure α-Fe exposed to low-energy high-flux D plasma Температурная зависимость поверхностной топографии и взаимодействия дейтерия с чистым железом при воздействии низкоэнергетической плазмы дейтерия высокой плотности Температурна залежність поверхневої топографії і взаємодії дейтерію з чистим залізом при дії низькоенергетичної плазми дейтерію високої густини Article published earlier |
| institution |
Digital Library of Periodicals of National Academy of Sciences of Ukraine |
| collection |
DSpace DC |
| title |
Temperature dependence of surface topography and deuterium interaction with a pure α-Fe exposed to low-energy high-flux D plasma |
| spellingShingle |
Temperature dependence of surface topography and deuterium interaction with a pure α-Fe exposed to low-energy high-flux D plasma Nikitin, A.V. Tolstolutskaya, C.D. Ruzhytskiy, V.V. Kopanets, I.E. Karpov, S.A. Vasilenko, R.L. Rostova, G.Y. Rybalchenko, N.D. Plasma dynamics and plasma-wall interaction |
| title_short |
Temperature dependence of surface topography and deuterium interaction with a pure α-Fe exposed to low-energy high-flux D plasma |
| title_full |
Temperature dependence of surface topography and deuterium interaction with a pure α-Fe exposed to low-energy high-flux D plasma |
| title_fullStr |
Temperature dependence of surface topography and deuterium interaction with a pure α-Fe exposed to low-energy high-flux D plasma |
| title_full_unstemmed |
Temperature dependence of surface topography and deuterium interaction with a pure α-Fe exposed to low-energy high-flux D plasma |
| title_sort |
temperature dependence of surface topography and deuterium interaction with a pure α-fe exposed to low-energy high-flux d plasma |
| author |
Nikitin, A.V. Tolstolutskaya, C.D. Ruzhytskiy, V.V. Kopanets, I.E. Karpov, S.A. Vasilenko, R.L. Rostova, G.Y. Rybalchenko, N.D. |
| author_facet |
Nikitin, A.V. Tolstolutskaya, C.D. Ruzhytskiy, V.V. Kopanets, I.E. Karpov, S.A. Vasilenko, R.L. Rostova, G.Y. Rybalchenko, N.D. |
| topic |
Plasma dynamics and plasma-wall interaction |
| topic_facet |
Plasma dynamics and plasma-wall interaction |
| publishDate |
2016 |
| language |
English |
| container_title |
Вопросы атомной науки и техники |
| publisher |
Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
| format |
Article |
| title_alt |
Температурная зависимость поверхностной топографии и взаимодействия дейтерия с чистым железом при воздействии низкоэнергетической плазмы дейтерия высокой плотности Температурна залежність поверхневої топографії і взаємодії дейтерію з чистим залізом при дії низькоенергетичної плазми дейтерію високої густини |
| description |
Surface topography and deuterium interaction with a-Fe under glow discharge hydrogen (deuterium) ions bombardment with energy of ~1 keV at ion fluencies of (0.02…1)∙10²⁴ D/m² and various temperatures have been examined. The methods used were scanning electron microscopy, thermal desorption spectroscopy and the D(³He,p) ⁴He nuclear reaction. Formation of blisters was observed in the temperature range 230…340 K. Roundshaped cavities contained small nonmetallic particles FexOy (x=1…2, y=1…4) were founded on the irradiated surface of α-Fe. Temperature dependence of average blister diameter, the deuterium depth profile and temperature of deuterium retention were studied
Изучена топография поверхности и взаимодействие дейтерия с a-Fe под воздействием тлеющего разряда ионов водорода (дейтерия) с энергией ~ 1 кэВ при ионных флюенсах (0,02…1)∙10²⁴ D/м² и различных температурах. Использовались методы сканирующей электронной микроскопии, термодесорбционной спектроскопии и ядерных реакций D(³He,p) ⁴He. В интервале температур 230…340 К наблюдалось образование блистеров. На облучённой поверхности -Fe были обнаружены полости округлой формы, содержащие небольшие неметаллические частицы FexOy (х=1…2, у=1…4). Обсуждаются: температурная зависимость среднего диаметра блистеров, распределение дейтерия по глубине образца и особенности удержания дейтерия.
Вивчено топографію поверхні і взаємодію дейтерію з a-Fe під впливом тліючого розряду іонів водню (дейтерію) з енергією ~ 1 кеВ при іонних флюенсах (0,02…1)∙10²⁴ D/м² і різних температурах. Використовувалися методи скануючої електронної мікроскопії, термодесорбційної спектроскопії і ядерних реакцій D(³He,p) ⁴He. В інтервалі температур 230…340 К спостерігалось утворення блістерів. На опроміненій поверхні -Fe були виявлені порожнини округлої форми, що містять невеликі неметалічні частки FexOy (х=1…2, у=1…4). Обговорюються: температурна залежність середнього діаметра блістерів, розподіл дейтерію по глибині зразка і особливості утримання дейтерію.
|
| issn |
1562-6016 |
| url |
https://nasplib.isofts.kiev.ua/handle/123456789/115453 |
| citation_txt |
Temperature dependence of surface topography and deuterium interaction with a pure α-Fe exposed to low-energy high-flux D plasma / A.V. Nikitin, G.D. Tolstolutskaya, V.V. Ruzhytskiy, I.E. Kopanets, S.A. Karpov, R.L. Vasilenko, G.Y. Rostova, N.D. Rybalchenko // Вопросы атомной науки и техники. — 2016. — № 6. — С. 117-120. — Бібліогр.: 8 назв. — англ. |
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2025-11-25T22:20:31Z |
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ISSN 1562-6016. ВАНТ. 2016. №6(106)
PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. 2016, № 6. Series: Plasma Physics (22), p. 117-120. 117
TEMPERATURE DEPENDENCE OF SURFACE TOPOGRAPHY AND
DEUTERIUM INTERACTION WITH A PURE -Fe EXPOSED TO
LOW-ENERGY HIGH-FLUX D PLASMA
A.V. Nikitin, G.D. Tolstolutskaya, V.V. Ruzhytskiy, I.E. Kopanets, S.A. Karpov,
R.L. Vasilenko, G.Y. Rostova, N.D. Rybalchenko
Institute of Solid State Physics, Material Science and Technology NSC KIPT,
Kharkov, Ukraine
E-mail: g.d.t@kipt.kharkov.ua
Surface topography and deuterium interaction with -Fe under glow discharge hydrogen (deuterium) ions
bombardment with energy of ~1 keV at ion fluencies of (0.02…1)∙10
24
D/m
2
and various temperatures have been
examined. The methods used were scanning electron microscopy, thermal desorption spectroscopy and the
D(
3
He,p)
4
He nuclear reaction. Formation of blisters was observed in the temperature range 230…340 K. Round-
shaped cavities contained small nonmetallic particles FexOy (x=1…2, y=1…4) were founded on the irradiated
surface of α-Fe. Temperature dependence of average blister diameter, the deuterium depth profile and temperature
of deuterium retention were studied.
PACS: 61.72.Cc, 68.55.Ln
INTRODUCTION
Sputtering-induced erosion of plasma-facing
materials (PFMs) is a serious concern for future
commercial reactors, not only for low Z materials, but
also for structural materials (ferritic steels, vanadium
alloys, etc.) [1].
Ferritic steels are currently considered as promising
materials for structural elements of both fission and
fusion reactors due to their higher resistance to void
swelling and irradiation creep as compared with
austenitic steels.
However, ferritic steels are known to be particularly
susceptible to nucleation of both blisters and associated
subsurface cracks arising during exposure to glow
discharge hydrogen plasma with ion energies of ~ 1 keV
[2]. Such low ion energies are known to be characteristic
of near-wall plasma fluxes in fusion reactors [3].
Blisters formed on the surface of the ferritic steel
look similar to blisters seen on the surface of metals
such as Nb, Сu, Ni, and stainless steel caused by light
ion bombardment (Н, D, Нe) [4]. But the dimensions of
plasma-induced blisters are two orders of magnitude
higher than the average dimensions of blisters produced
at ion beam energy of ~1 keV. The majority of blisters
in the current study have a dome-like shape, with the
ratio of height to diameter around 0.02…0.05.
In glow discharge experiments it was shown that the
critical fluence of first blister formation strongly
depends on the target temperature and the deformation
level of the alloy [1]. There is insufficient understanding
concerning the influence of hydrogen plasma on the
concurrent formation of cracks and blisters in ferritic-
martensitic steels and requires further investigation.
It is anticipated that the surface and near-surface
structural-phase microstructure of a particular alloy may
affect the various erosion processes. Accordingly it is
desirable to investigate a material with approximately
uniform structure and monatomic composition, e.g. -Fe.
The goal of this paper is to investigate the evolution
of surface topography and the features of deuterium
interaction with -Fe under glow discharge deuterium
ions bombardment with energy of ~ 1 keV at ion
fluencies of (0.02…1)·10
24
D/m
2
and various tempera-
tures.
1. MATERIAL AND METHODS
The samples of -Fe (bcc) with a purity of 99.9 wt%
were recrystallized at 1600 K after rolling and cutting. It
contains impurities of more than a dozen elements. The
carbon and copper concentration are of about 0.02% and
0.1 %, respectively. The remaining elements are in
thousandths of a percent.
The specimens with dimensions of 10 7 mm were
cut from a sheet with thickness of 1 mm. The surface of
each sample was polished mechanically and then
electropolished in a standard electrolyte to remove any
mechanically damaged near-surface layer.
The specimens have been irradiated at various
temperatures with deuterium ions using glow gas-
discharge plasma electrodes at 1000 V, producing an
ion flux of 10
19
D/(m
2
∙s). In this study we chose D in
order to easily measure the depth dependence of the
implanted and diffused hydrogen. The maximum
irradiation fluence was 1·10
24
D/m
2
.
The main parameter changed in the experimental
series was the temperature during plasma exposure,
which was varied between 240 and 300 K. The
specimen was placed in a resistively-heated holder. The
specimen temperature was continuously monitored
using a thermocouple in the base of the specimen holder
and was attached to the lower surface of specimen.
Temperature maintenance on the steel samples in this
device was achieved either by resistive heating or liquid
nitrogen cooling. The temperature was maintained to
within ±2.5 K. A detailed schematic diagram of the
experimental setup is presented in Ref. [1].
The D concentration in the plasma-exposed Fe
samples was measured by means of the D(
3
He,α)H
reaction, where protons were analyzed. To determine
the D concentration at larger depths, an analyzing beam
of
3
He ions with energies varied from 0.3 to 1.4 MeV
118 ISSN 1562-6016. ВАНТ. 2016. №6(106)
was used. The proton yields measured at different
3
He
ion energies allow measuring the D depth profile at
depths of up to 2 μm.
Total deuterium retention in the Fe samples was
monitored ex-situ using thermal desorption
spectrometry (TDS). A resistive heater was used to heat
the samples at a ramp rate of 6 K/s and the sample
temperature was raised to 1300 K. D2 molecules
released during TDS run were monitored by monopole
mass spectrometer.
A JEOL JSM-7001F 00 scanning electron
microscope was used to study the surface morphology.
Investigations of surface microstructure were performed
using a ММО-1600-АТ metallographic microscope.
2. RESULTS AND DISCUSSION
Fig. 1 shows SEM images of surface morphology of
initial -Fe after etching in 5 % nitric acid with water.
Etching pits at the exit of dislocations on the surface,
and pits with inclusions were observed.
Fig. 1. SEM image of -Fe initial surface after etching
and EDS X-ray spectrums of different part of surface
The inclusions can be introduced during the
preparation of samples for the experiment (cutting,
rolling, annealing and the mechanical and electrolytic
polishing) or the accumulation of impurities that have
"slided" to the dislocation core. EDS analyses revealed
that these particles are FexOy, where x=1…2, y=1…4.
The SEM images of the -Fe sample exposed to the
fluence of 1·10
24
D/m
2
at temperatures in the range
240…300 K are shown in Fig. 2. The surface is covered
by a large number of blisters having an irregular shape.
Video registration shows that small blisters with
diameters of 2 microns grow in the initial stage and then
later blisters having diameters on the order of
60 microns began to develop. All blisters are limited by
the grain boundaries.
Fig. 3 shows the temperature dependence of average
diameters and density of blisters formed under
deuterium plasma. A minimum of two samples were
used at each temperature. The average diameter and
density of blisters increases monotonically (density of
blisters increases weakly) with increasing temperature
of irradiation up to 250…260 K and then decrease.
The large blisters showed a multi-layered structure
like steps (Fig. 4). This effect is most pronounced at the
irradiation temperature of 270 K.
a
b
100 m
c
Fig. 2. SEM images of blisters on the surface of -Fe
after irradiation with deuterium plasma to 1·10
24
D/m
2
at 240 (a), 270 (b) and 285 (c). The scale is the same for
all micrographs (a – c)
220 230 240 250 260 270 280 290
0
10
20
30
40
0
5
10
15
A
v
e
ra
g
e
s
iz
e
,
m
Temperature, K
D
e
n
s
it
y
,
x
1
0
3
Fig. 3. Temperature dependence of average diameter
and density of blisters formed under deuterium plasma
irradiation to 1·10
24
D/m
2
for -Fe
ISSN 1562-6016. ВАНТ. 2016. №6(106) 119
Fig. 4. SEM images of a multi-layered structure like
steps (45° tilt) appearing on -Fe exposed to the fluence
of 1·10
24
D/m
2
at 270 K
It has been considered that the high-dome blisters
are formed by deuterium-promoted local superplasticity
[5]. First, deuterium-induced vacancies are generated
due to the lowering of vacancy formation energy caused
by trapping of deuterium [6]. Subsequently deuterium-
vacancy clusters are formed and diffuse deeply into the
bulk such as somewhere near the surface in the grains
and grain boundaries and agglomerate, resulting in
blisters. In addition, every agglomeration of the
deuterium-vacancy clusters results in a step print on the
blister [7].
The penetration of deuterium on the depth orders of
magnitude greater than the calculated ion range
confirms the data obtained by the NRA. Fig. 5 presents
the depth distribution profiles of deuterium in -Fe
exposed to 1 keV deuterium plasma.
0.0 0.2 0.4 0.6 0.8 1.0 1.2 1.4 1.6
0.0
0.1
0.2
0.3
0.4
0.5
D
c
o
n
c
e
n
tr
a
ti
o
n
,
a
t.
%
Depth, m
1
2
Fig. 5. Profiles of deuterium in -Fe exposed to
deuterium plasma at 300 K to a doses of 5·10
23
(1)
and 4·10
22
(2) D/m
2
The calculated normal-incident range of 0.5 keV D
+
in iron is about 7 nm. Detection of deuterium at a depth
of 1.7 μm confirms that the implanted D migrates into
the bulk far beyond the ion range and thereby promotes
nucleation of blister gaps at this depth. At fluence
5·10
23
D2
+
/m
2
the deuterium concentration in sub-
surface layer reaches 0.5 at.% and becomes enough for
blister formation.
Glow gas-discharge D plasma irradiation simul-
taneously with blisters causes the formation of large round-
shaped cavities on the surface of Fe. Fig. 6 shows that
almost all of large cavities contained small nonmetallic
particles. EDS analyses revealed that these particles are
FexOy, where x=1…2, y=1…4. The diameter of the
cavities (~ 1 micron) correlates with the size of the
inclusions. The discarded material "plug" consists of
pure Fe.
a
b
Fe
Fe2O3
c
Fig. 6. SEM images of round-shaped cavities on the
surface of -Fe after irradiation with deuterium plasma
to 1·10
24
D/m
2
at 270 K with different scale for
micrographs a – c. EDS X-ray spectrums of inclusion
and extruded material are shown in the insert of Fig. 6,c
It can be assumed that the deuterium trapping by
these inclusions promotes gas atoms combination to
form hydrogen molecules that will exert a pressure on
the surrounding -Fe, resulting in extrusion of material
and the formation of round-shaped cavities.
The strong trapping of deuterium on the inclusions may
indicate the data obtained by TDS. Fig. 7 shows desorption
of deuterium from -Fe exposed to deuterium plasma at
300 K to a dose of 1·10
24
D/m
2
. The release of deuterium
from iron sample starts at ~ 330 K. The maximum of
desorption peak is observed at 500 K.
As can be seen from Fig. 2, blisters formed at
different temperatures of irradiation have bursting
covers whereby the deuterium should release from
fissures. According to [8] deuterium is not retained in
solution or nor radiation-induced point defects near
room temperature irradiation in -Fe. Deuterium release
at T~500 K may indicate gas de-trapping from detected
inclusions. To confirm the observed effect additional
studies are needed.
120 ISSN 1562-6016. ВАНТ. 2016. №6(106)
400 600 800 1000
0.0
0.2
0.4
0.6
0.8
1.0
D
e
s
o
rp
ti
o
n
r
a
te
,
u
rb
.
u
n
it
s
Temperature, K
Fig. 7. TDS spectra of D2 from -Fe exposed to
deuterium plasma to a dose of 1·10
24
D/m
2
at 300 K
CONCLUSIONS
Surface topography and deuterium interaction with
-Fe under glow discharge deuterium ions
bombardment and various temperatures have been
examined. Real-time monitoring of the target surface
was performed with a set of in-situ optical surface
diagnostics that allows detection of the first appearance
of blisters and their subsequent growth. The conclusions
to be drawn from this work are as follows.
Exposure of α-Fe to low-energy ( 1 keV) and high
flux (10
19
D/(m
2
∙s)) plasma to fluence of ~ 1·10
24
D/m
2
leads to the formation of blisters.
It is suggested that hydrogen atoms diffuse to low
free energy locations such as the interface of matrix and
inclusions. At these locations, the hydrogen atoms can
combine to form hydrogen gas molecules that exert
pressure on the surrounding metal, thereby forming a
blister.
Round-shaped cavities contained small nonmetallic
particles FexOy (x=1…2, y=1…4) were founded on the
irradiated surface of α-Fe. This phenomenon was not
observed for EP-450 F/M steel under the same
conditions of plasma exposure.
REFERENCES
1. A.V. Nikitin et al. Blister formation on
13Cr2MoNbVB ferritic-martensitic steel exposed to
hydrogen plasma // Jornal of Nucl. Mater. 2016, v. 478,
p. 26-31.
2. V.I. Bendikov, A.V. Nikitin, O.A. Opalev,
V.V. Ruzhitskii, V.F. Rybalko, S.M. Khazan. Crack
formation in the 12Kh12M1BFR ferritic steel under the
action of hydrogen ion flux //Atomic Energy. 1990,
v. 68 (6), p. 465-469.
3. R.W. Conn, J. Kesner. Plasma modeling and first
wall interaction phenomena in tokamaks // Journal of
Nucl. Mater. 1976, v. 63, p. 1.
4. R. Behrisch. Surface erosion from plasma materials
interaction // Journal of Nucl. Mater. 1979, v. 85-86,
p. 1047-1061.
5. W.M. Shu, E. Wakai, T. Yamanishi. Blister bursting
and deuterium bursting release from tungsten exposed
to high fluences of high flux and low energy deuterium
plasma // Nucl. Fusion. 2007, v. 47, p. 201-209.
6. Y. Fukai, N. Okuma. Formation of Superabundant
Vacancies in Pd Hydride under High Hydrogen
Pressures // Phys. Rev. Letters. 1994, v. 73, № 12,
p. 1640-1643.
7. W. M. Shu. High-dome blisters formed by deuterium-
induced local superplasticity // Applied Physics Letters.
2008, v. 92, p. 211904.
8. S.M. Myers, S.T. Picraux, et. al. Defect trapping of
ion-implanted deuterium in Fe // J. Appl. Phys. 1979,
v. 50, № 9, p. 5710-5719.
Article received 23.11.2016
ТЕМПЕРАТУРНАЯ ЗАВИСИМОСТЬ ПОВЕРХНОСТНОЙ ТОПОГРАФИИ И ВЗАИМОДЕЙСТВИЯ
ДЕЙТЕРИЯ С ЧИСТЫМ ЖЕЛЕЗОМ ПРИ ВОЗДЕЙСТВИИ НИЗКОЭНЕРГЕТИЧЕСКОЙ ПЛАЗМЫ
ДЕЙТЕРИЯ ВЫСОКОЙ ПЛОТНОСТИ
А.В. Никитин, Г.Д. Толстолуцкая, В.В. Ружицкий, И.Е. Копанец, С.А. Карпов, Р.Л. Василенко,
А.Ю. Ростова, Н.Д. Рыбальченко
Изучена топография поверхности и взаимодействие дейтерия с -Fe под воздействием тлеющего разряда
ионов водорода (дейтерия) с энергией ~ 1 кэВ при ионных флюенсах (0,02…1)∙10
24
D/м
2
и различных
температурах. Использовались методы сканирующей электронной микроскопии, термодесорбционной
спектроскопии и ядерных реакций D(
3
Не,р)
4
Не. В интервале температур 230…340 К наблюдалось
образование блистеров. На облучённой поверхности -Fe были обнаружены полости округлой формы,
содержащие небольшие неметаллические частицы FexOy (х=1…2, у=1…4). Обсуждаются: температурная
зависимость среднего диаметра блистеров, распределение дейтерия по глубине образца и особенности
удержания дейтерия.
ТЕМПЕРАТУРНА ЗАЛЕЖНІСТЬ ПОВЕРХНЕВОЇ ТОПОГРАФІЇ І ВЗАЄМОДІЇ ДЕЙТЕРІЮ
З ЧИСТИМ ЗАЛІЗОМ ПРИ ДІЇ НИЗЬКОЕНЕРГЕТИЧНОЇ ПЛАЗМИ ДЕЙТЕРІЮ ВИСОКОЇ ГУСТИНИ
А.В. Нікітін, Г.Д. Толстолуцька, В.В. Ружицький, І.Є. Копанець, С.О. Карпов, Р.Л. Василенко,
Г.Ю. Ростова, Н.Д. Рибальченко
Вивчено топографію поверхні і взаємодію дейтерію з -Fe під впливом тліючого розряду іонів водню
(дейтерію) з енергією ~ 1 кеВ при іонних флюенсах (0,02…1)∙10
24
D/м
2
і різних температурах.
Використовувалися методи скануючої електронної мікроскопії, термодесорбційної спектроскопії і ядерних
реакцій D(
3
Не,р)
4
Не. В інтервалі температур 230…340 К спостерігалось утворення блістерів. На опроміненій
поверхні -Fe були виявлені порожнини округлої форми, що містять невеликі неметалічні частки FexOy
(х=1…2, у=1…4). Обговорюються: температурна залежність середнього діаметра блістерів, розподіл
дейтерію по глибині зразка і особливості утримання дейтерію.
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