The effect OF Cr, Cr-N and Cr-Ox coatings on deuterium retention and penetration in zirconium alloy Zr-1Nb
Depth distribution profiles of deuterium in zirconium alloy Zr-1Nb in initial state and with coatings Cr, CrN, and Cr₂O₃ after ion implantation with 15 keV/D⁺ at temperatures 350 °C to dose 1·10¹⁷ D/cm⁻² and deuterium plasma of glow discharge at room temperature are determined by the method of nucle...
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| Date: | 2015 |
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Національний науковий центр «Харківський фізико-технічний інститут» НАН України
2015
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| Cite this: | The effect OF Cr, Cr-N and Cr-Ox coatings on deuterium retention and penetration in zirconium alloy Zr-1Nb / I.E. Kopanetz, G.D. Tolstolutskaya, A.V. Nikitin, V.A. Bilous, A.S. Kuprin, V.D. Ovcharenko, R.L. Vasilenko // Вопросы атомной науки и техники. — 2015. — № 5. — С. 81-86. — Бібліогр.: 16 назв. — англ. |
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Digital Library of Periodicals of National Academy of Sciences of Ukraine| _version_ | 1860262052369530880 |
|---|---|
| author | Kopanetz, I.E. Tolstolutskaya, G.D. Nikitin, A.V. Bilous, V.A. Kuprin, A.S. Ovcharenko, V.D. Vasilenko, R.L. |
| author_facet | Kopanetz, I.E. Tolstolutskaya, G.D. Nikitin, A.V. Bilous, V.A. Kuprin, A.S. Ovcharenko, V.D. Vasilenko, R.L. |
| citation_txt | The effect OF Cr, Cr-N and Cr-Ox coatings on deuterium retention and penetration in zirconium alloy Zr-1Nb / I.E. Kopanetz, G.D. Tolstolutskaya, A.V. Nikitin, V.A. Bilous, A.S. Kuprin, V.D. Ovcharenko, R.L. Vasilenko // Вопросы атомной науки и техники. — 2015. — № 5. — С. 81-86. — Бібліогр.: 16 назв. — англ. |
| collection | DSpace DC |
| container_title | Вопросы атомной науки и техники |
| description | Depth distribution profiles of deuterium in zirconium alloy Zr-1Nb in initial state and with coatings Cr, CrN, and Cr₂O₃ after ion implantation with 15 keV/D⁺ at temperatures 350 °C to dose 1·10¹⁷ D/cm⁻² and deuterium plasma of glow discharge at room temperature are determined by the method of nuclear reactions. It is shown that in studied range of temperatures and concentrations of deuterium coatings CrN and Cr₂O₃ act as barrier and protect zirconium from interaction with hydrogen isotope.
У вихідному сплаві цирконію і в сплаві з Cr-, CrN- и Cr₂O₃-покриттями методом ядерних реакцій виміряні профілі розподілу дейтерію, який імплантований з енергією 15 кеВ/D⁺ при температурі 350 °С до дози 1·10¹⁷ D/см⁻² і впроваджений при впливі плазми тліючого розряду. Показано, що в дослідженому інтервалі температур і концентрацій покриття CrN и Cr₂O₃ виступають бар'єром і захищають цирконій від взаємодії з ізотопом водню - дейтерієм.
В исходном сплаве циркония и в сплаве с Cr-, CrN- и Cr₂O₃-покрытиями методом ядерных реакций измерены профили распределения дейтерия, имплантированного с энергией 15 кэВ/D⁺ при температуре 350 °С до дозы 1·10¹⁷ D/см⁻² и внедренного при воздействии плазмы тлеющего разряда. Показано, что в исследованном интервале температур и концентраций покрытия CrN и Cr₂O₃ выступают барьером и защищают цирконий от взаимодействия с изотопом водорода - дейтерием.
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| first_indexed | 2025-12-07T18:56:28Z |
| format | Article |
| fulltext |
ISSN 1562-6016. PASТ. 2015. №5(99), p. 81
UDC 669.296.004.0772
THE EFFECT OF Cr, Cr-N AND Cr-Ox COATINGS ON DEUTERIUM
RETENTION AND PENETRATION IN ZIRCONIUM ALLOY Zr-1Nb
I.E. Kopanetz, G.D. Tolstolutskaya, A.V. Nikitin, V.A. Bilous, A.S. Kuprin,
V.D. Ovcharenko, R.L. Vasilenko
Institute of Solid state Physics, Material Science and Technology NSC KIPT
Kharkov, Ukraine
Depth distribution profiles of deuterium in zirconium alloy Zr-1Nb in initial state and with coatings Cr, CrN, and
Cr2O3 after ion implantation with 15 keV/D
+
at temperatures 350 °C to dose 1·10
17
D/cm
-2
and deuterium plasma of
glow discharge at room temperature are determined by the method of nuclear reactions. It is shown that in studied
range of temperatures and concentrations of deuterium coatings CrN and Cr2O3 act as barrier and protect zirconium
from interaction with hydrogen isotope.
1. INTRODUCTION
Zirconium and its alloys play an important role in
the nuclear field, given an optimized set of neutronic
and mechanical properties [1]. However the mixture
hydrogen is produced in the result of interaction of
zirconium with coolant of water-cooled energetic
nuclear reactors and as result nucleation and formation
of hydride precipitates in zirconium alloys have been a
key factor in limiting the lifetime of nuclear fuel
cladding [2–5].
In order to solve this problem the barrier layers for
hydrogen diffusion by modification of surface by ion-
plasma treatment which includes irradiation of surface
by gaseous and metal ions and deposition of vacuum-arc
condensates are produced [6, 7]. To select the best
coatings it is important to have a detailed understanding
of the effect of coatings on hydrogen behavior.
In a recent study [8] we were described the
methodology of determination of thickness and
composition of plasma coatings of titanium and
chromium nitrides obtained at different pressure of
nitrogen in discharge chamber of plasma assembly.
The methods of saturation with deuterium
(hydrogen) from gaseous phase and determination of its
depth distribution profiles in zirconium alloy in initial
state and in zirconium with coatings also are shown.
The substitution of deuterium for protium allows the use
of nuclear reactions to determine the depth distribution
and concentration of hydrogen isotopes.
Permeability of coatings of CrN, CrAl, and Al2O3 on
specimens of alloy Zr-1Nb in conditions of their
saturation with deuterium was studied [9]. It was
determined that in studied range of temperatures and
pressures of deuterium the coating plays the role of
barrier and protects zirconium from interaction with
isotope of hydrogen.
During saturation of specimens by deuterium from
gaseous phase deuterium doesn’t penetrate in coating
volume. Its near surface adsorption is detected. Up to
550 °C the amount of penetrated deuterium in the
coatings is two and at Tsat = 550 °C even three orders
less than for Zr-1Nb without coating.
It was shown [10, 11], that the vacuum-arc coatings
of chromium and Cr-N effectively prevent oxidation of
Zr-1Nb alloy tubes. Arc Ion Plating Technique produces
Cr-O coating with high oxidation resistance and good
mechanical properties [12], which can provide the
fretting-corrosion protection of fuel tubes in the nuclear
reactor under normal operating conditions.
In addition to protecting the zirconium alloys from
reacting with hydrogen the coatings can be used as an
effective way to reduce tritium permeation through
blanket components in a fusion device 13. The
application of a thin metal coating assumed to reduce
tritium retention and permeation in
3
He tubes used in
the accelerator production of tritium (APT) device 14.
It is clearly important to study the behavior of hydrogen
isotopes in materials under irradiation and at high
concentrations.
The goal of present work was to investigate the
effect of Cr, CrN, and Cr2O3 coatings on retention and
permeation of deuterium through zirconium alloy
Zr-1Nb at introduction of deuterium in the sample by
way of ion implantation or plasma of glow discharge.
2. EXPERIMENTAL
Chromium coatings were deposited by the vacuum
arc method from the two counter flows of metallic
plasma with planetary rotation of samples on the system
axis.
Chromium (99.9%) was used as cathodes. The
temperature of samples during deposition did not
exceed 500 °С. The initial vacuum in the system was at
a level Р0 ≈ 7·10
-4
Pа. The coating thickness was
≈ 1.5…5 μm. During deposition of Cr-N and Cr-O
coatings, the working pressure was kept at 2 Pa by
introducing reactive gas N2 and O2, respectively.
Coatings were deposited on flat specimens
(5×14×0.7 mm) produced from section of fuel tubes
(alloy Zr-1Nb).
Before the deposition of coatings the surface of
specimens was bombarded by ions of argon and
chromium at negative potential from 0.5 to 1.35 kV.
Implantation of specimens by deuterium with
energies 15 keV/D
+
was performed by means of
irradiation facility a schematic diagram of which is
shown in Fig. 1.
The facility has an oil-free pumping system with a
residual target-chamber pressure of ~ 110
-4
Pa. The
deuterium ion flux was 10
14
cm
-2
∙s
-1
, dose – 1·10
17
D/cm
-2
.
The implantation temperature supported at 350 °C.
1 2 3 4
6 7
8 9 10
11 5
D
+
Fig. 1. Diagram of irradiation facility:
1 – base chamber; 2 – Faraday cup; 3 – accelerating
system; 4, 5 – ion injector with a gas inlet system;
6 – electrical power supply for the ion injector;
7 – high-voltage power supply 0…50 kV;
8, 9 – vacuum-pumping system; 10 – bedplate;
11 – magnetic mass-analyzer; the dotted line with an
arrow the path of the ion beam D
+
After cooling of specimens to room temperature the
content of deuterium was measured by the method of
nuclear reactions. The depth distribution profile of
deuterium was measured by reaction D(
3
He,p)
4
He.
Beams of ions
3
He
+
with energies 0.3…1.4 MeV were
obtained
with electrostatic accelerator ESU-2. The result
of nuclear reaction (
3
He, D) is the birth of two particles:
of proton and
4
He. For investigation of high depths the
method of nuclear reactions (NRA) in geometry of back
scattering with analysis of protons energy spectra is
more beneficial. More detailed description of the
method of deuterium concentration measurement in
materials is presented in [8].
For study of surface morphology the scanning
electron microscope JEOLJSM-7001F 00 was used.
3. RESULTS AND DISCUSSION
For testing of the methods of irradiation and further
comparison of deuterium penetration in zirconium alloy
with and without coating the retention and permeation
of deuterium through zirconium alloy Zr-1Nb was
firstly investigated. It is known that in studied range of
temperatures hydrogen and its isotopes have high
mobility in zirconium alloy [3].
Fig. 2 shows the depth distribution profiles of
deuterium in alloy Zr-1Nb irradiated 15 keV/D
+
at
temperatures 350 °C to dose 1·10
17
D/cm
-2
. Data are
shown for two types of initial samples with preliminary
ion cleaning of sample surface and without.
It is seen that deuterium is detected over the entire
depth available for the analyzing ions of
3
He
+
with
energy 1.4 MeV (probe depth). The depth profile can be
divided into two parts: a peak at 0 depth with a decaying
curve having a half-width of about 250 nm. Another
part of the implanted gas (concentration of about
100 appm) is practically uniform distributed up to a
depth of 2.5 m.
0.0 0.2 0.4 0.6 0.8 1.0 1.2 1.4 1.6 1.8 2.0 2.2 2.4
0.00
0.01
0.02
0.03
0.04
0.05
0.06
0.07
C
o
n
c
e
n
tr
a
ti
o
n
,
a
t.
%
Depth, m
Fig. 2. Depth distribution profile of deuterium ion-
implanted with the energy 15 keV/D at a temperature of
350 °C to dose 1·10
17
cm
-2
in initial Zr-1Nb
(without coatings)
The peaks of the depth distribution profiles and the
respective half-widths practically agree with the SRIM
code simulations [15], indicating that a fraction of the
implanted deuterium is trapped by the damage produced
during self-implantation, even though the deuterium-
induced dose is less than 1 dpa. The remaining part of
deuterium is captured on the traps of no radiation origin
and it may be distributed to depths much greater than
depth of analysis.
Pre-ion cleaning makes a noticeable effect in the
retention and distribution of ion-implanted deuterium.
Fig. 3 shows the depth distribution profiles of
deuterium implanted with 15 keV/D
+
at temperatures
350 °C to dose 1·10
17
D/cm
-2
in chromium coatings on a
Zr-1Nb substrate. Data are shown for two thicknesses of
the chromium coatings – 1.5 and 3.5 m.
0,0 0,2 0,4 0,6 0,8 1,0 1,2 1,4 1,6 1,8
0,000
0,005
0,010
0,015
0,020
0,025
0,030
D
c
o
n
c
e
n
tr
a
ti
o
n
,
a
t.
%
Depth, m
Fig. 3. Depth distribution profile of deuterium ion-
implanted with the energy 15 keV/D at a temperature of
350 °C to dose 1·10
17
cm
-2
in Zr-1Nb with Cr coating
thickness 1.5 (■) and 3.5 m (о)
The figure shows the distribution of deuterium only
in the near-surface region for the chromium coatings
and a decrease in almost twice of magnitude of
concentration of captured deuterium in comparison with
the alloy Zr-1Nb. These facts indicate low retention of
deuterium in the traps at the irradiation temperature
350 °C.
Fig. 4 shows depth distribution profiles of deuterium
ion-implanted in Cr coating with the energy 15 keV/D
+
at room temperature and subsequent annealed at 350 °C.
0,0 0,5 1,0 1,5 2,0
0,00
0,01
0,02
0,03
0,04
D
c
o
n
c
e
n
tr
a
ti
o
n
,
а
т.
%
Depth, m
Zr
x5
Cr
Fig. 4. Depth distribution profile of deuterium ion-
implanted with the energy 15 keV/D at a room
temperature to dose 1·10
17
cm
-2
(■) and subsequent
annealing at 350 °C (о) in Zr-1Nb with Cr coating
thickness 1.5 m
Irradiation at room temperature causes the retention
of nearly 80% of implanted deuterium. It is observed a
peak at 0 depth and “tail” of deuterium distribution in
the material. Since the coating had a thickness of
1.5 m, the deuterium penetrated through the Cr coating
into the substrate of an alloy Zr-1Nb. After annealing,
the deuterium concentration decreased about five times
on all depth in coating and Zr-1Nb substrate.
As can be seen from Fig. 3 the two-fold difference
of the concentration of deuterium trapped chromium
coating with different thicknesses – 1.5 and 3.5 m are
observed.
It is known that the process of hydrogen
dissociation/association at metal-vacuum interface has a
significant influence on hydrogen retention in metals.
The back release is possible only through the formation
of hydrogen molecule by way of surface recombination.
The latter is governed by physical-chemical
mechanisms that are highly sensitive to the surface
condition and, in particular, to the surface chemical
composition at the level of a fraction of a monolayer.
Fig. 5 shows microphotographs of surface of Cr
coatings where any special features of surface
morphology are not seen. A more detailed study will
provide the new results needed to understand of the
effect of chromium coatings on retention and
permeation of deuterium under ion irradiation.
Fig. 6 shows the depth distribution profiles of
deuterium in Cr2O3 and CrN coating on a Zr-1Nb
substrate irradiated 15 keV/D
+
at temperatures 350 °C to
dose 1·10
17
D/cm
-2
. As can see in these coatings the
deuterium remained in a depth which corresponds to the
calculated ranges of deuterium ions with energy of
15 keV. The retention is about 90% of implanted
deuterium.
a
b
Fig. 5. Microphotographs of the surface of Cr coatings
with thickness of 1.5 (a) and 3.5 m (b)
0.0 0.2 0.4 0.6 0.8 1.0 1.2 1.4 1.6
0.00
0.01
0.02
0.03
0.04
0.05
0.06
D
c
o
n
c
e
n
tr
a
ti
o
n
,
a
t.
%
Depth, m
Fig. 6. Depth distribution profile of deuterium ion-
implanted with the energy 15 keV/D at 350 °C to dose
1·10
17
cm
-2
in Cr2O3 (■) and CrN (o) coatings
Both coatings exhibit the same character of
deuterium retention in the range profile, although the
structure of the surface of these coatings is somewhat
different (Fig. 7).
As noted in the introduction coatings may be used as
an effective way to reduce tritium permeation in a
fusion device and in
3
He tubes used in the accelerator
production of tritium (APT) device. The tritium gas
pressure that will exist within both types of devices and
the continuous tritium injection into the walls raise a
valid concern about tritium retention and/or permeation
through the walls into surrounding cooling water.
Neither of these conditions is desirable for devices
operation. Holdup in the walls will make it difficult for
device to meet its production goals and extract the
tritium from the walls. High levels of permeation will
necessitate a costly tritium removal system for the
cooling water.
a
b
Fig. 7. Microphotographs of the surface of Cr2O3 (a)
and CrN (b) coatings with thickness of 5 m
In presented paper we investigated the retention and
permeation of deuterium through Cr, CrN and Cr2O3
coatings under the influence of deuterium glow gas-
discharge plasma. Deuterium was used for these
experiments, because the migration of deuterium and
tritium through materials is very similar 16.
Specimens were irradiated with deuterium ions from
glow gas-discharge plasma at voltage on electrodes
1000 V and density of ion current 20 A/m
2
. Maximal
irradiation dose was 1·10
19
D2
+
/cm
2
. The specimens
were irradiated at room temperature.
0.0 0.5 1.0 1.5 2.0 2.5
0
20
40
60
80
100
D
c
o
n
c
e
n
tr
a
ti
o
n
,
a
t%
Depth, m
Zr1NbCr
Fig. 8. Depth distribution profile of deuterium for Cr
coatings after exposed to a deuterium plasma at room
temperatures to dose 1·10
19
D2
+
/cm
-2
Fig. 8 shows the depth distribution profiles of
deuterium for Cr coating with thickness 1.5 m exposed
to a deuterium plasma at room temperatures to dose
1·10
19
D2
+
/cm
-2
.
Almost 30% of implanted deuterium atoms are
trapped on region between 0.8 and 2.5 m. Retention in
Cr coating is very low and a small peak attributed to
deuterium absorption on surface is present at 0-depth.
As shown in Fig. 8 the thickness of Cr coating
decreased almost twice. The reason for such effects
likely involves effects of sputtering. This assumption is
confirmed by comparing the structure of the surface of
the original coating and after plasma exposure (Fig. 9).
It is seen that the surface sputtered.
Thus chromium coating shows weak trapping of
deuterium (see Fig. 3), which could be considered as a
positive feature, but at the same time because of the
good permeability at saturation of the plasma, can not
be considered a good protective coating.
a
b
Fig. 9. Microphotographs of the surface of Cr coatings
initial (a) and after exposed to a deuterium plasma
at room temperatures to dose 1·10
19
D2
+
/cm
-2
(b)
Fig. 10 shows the depth distribution profiles of
deuterium for Cr2O3 and CrN coatings with thickness
5 m exposed to a deuterium plasma at room
temperatures to dose 1·10
19
D2
+
/cm
-2
.
It is seen that deuterium atoms are trapped near the
surface. The quantity of trapped deuterium is about
0.35% of implanted deuterium dose. The lower
deuterium retention and permeation in Cr2O3 and CrN
coatings may be due to several effects.
As noted above if the coating material has a higher
recombination rate coefficient for deuterium than the
bulk material, the deuterium release from the surface
should be increased, lowering the deuterium
concentration. The coating may have poor solubility of
deuterium. A reduction in the concentration at the near
surface may be associated with effects of sputtering due
to the high density of ion flux. A more detailed study
will need to understand of the effect of CrN and Cr2O3
coatings on retention and permeation of deuterium
under ion irradiation.
0.0 0.2 0.4 0.6 0.8 1.0 1.2 1.4 1.6
0.00
0.02
0.04
0.06
0.08
0.10
0.12
0.14
0.16
0.18
D
c
o
n
c
e
n
tr
a
ti
o
n
,
a
t%
Depth, m
1
2
Fig. 10. Depth distribution profile of deuterium
for Cr2O3 (1) and CrN (2) coatings after exposed to
a deuterium plasma at room temperatures to dose
1·10
19
D2
+
/cm
-2
CONCLUSION
The depth distribution profiles of deuterium in
zirconium alloy Zr-1Nb in initial state and with coatings
Cr, CrN and Cr2O3 were observed by the NRA method.
The effect of vacuum-arc coatings on retention and
penetration of deuterium in zirconium alloy Zr-1Nb at
introduction of deuterium in the sample by way of ion
implantation or plasma of glow discharge was
investigated.
It is found that the pure chromium coatings with
thickness of 1.5 μm provide a low retention of
deuterium in the traps at the irradiation temperature
350 °C. At the same time, they show high permeability
at irradiation with high-density plasma flux.
The CrN and Cr2O3 coatings significantly reduce the
hydrogen (and its isotopes) permeation into material
when introduced both by ion implantation method and
by plasma glow discharge. In these coatings
experimental depth profile of deuterium correlates to the
calculated distribution of implanted D
+
ions, so the
deuterium does not leave the implanted layer.
These results indicate that CrN and Cr2O3 coatings
should be effective for use in nuclear devices.
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ВЛИЯНИЕ ПОКРЫТИЙ Cr, Cr-N и Cr-Ox НА УДЕРЖАНИЕ И ПРОНИКНОВЕНИЕ
ДЕЙТЕРИЯ В СПЛАВЫ ЦИРКОНИЯ Zr-1Nb
И.Е. Копанец, Г.Д. Толстолуцкая, А.В. Никитин, В.А. Белоус, А.С. Куприн,
В.Д. Овчаренко, Р.Л. Василенко
В исходном сплаве циркония и в сплаве с Cr-, CrN- и Cr2O3-покрытиями методом ядерных реакций
измерены профили распределения дейтерия, имплантированного с энергией 15 кэВ/D
+
при температуре
350 °С до дозы 1·10
17
D/см
-2
и внедренного при воздействии плазмы тлеющего разряда. Показано, что в
исследованном интервале температур и концентраций покрытия CrN и Cr2O3 выступают барьером и
защищают цирконий от взаимодействия с изотопом водорода дейтерием.
ВПЛИВ ПОКРИТТІВ Cr, Cr-N та Cr-Ox НА УТРИМАННЯ І ПРОНИКНЕННЯ ДЕЙТЕРІЮ
В СПЛАВИ ЦИРКОНІЮ Zr-1Nb
І.Є. Копанець, Г.Д. Толстолуцька, А.В. Нікітін, В.А. Білоус, О.С. Купрін,
В.Д. Овчаренко, Р.Л. Василенко
У вихідному сплаві цирконію і в сплаві з Cr-, CrN- и Cr2O3-покриттями методом ядерних реакцій
виміряні профілі розподілу дейтерію, який імплантований з енергією 15 кеВ/D
+
при температурі 350 °С до
дози 1·10
17
D/см
-2
і впроваджений при впливі плазми тліючого розряду. Показано, що в дослідженому
інтервалі температур і концентрацій покриття CrN и Cr2O3 виступають бар'єром і захищають цирконій від
взаємодії з ізотопом водню дейтерієм.
|
| id | nasplib_isofts_kiev_ua-123456789-112288 |
| institution | Digital Library of Periodicals of National Academy of Sciences of Ukraine |
| issn | 1562-6016 |
| language | English |
| last_indexed | 2025-12-07T18:56:28Z |
| publishDate | 2015 |
| publisher | Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
| record_format | dspace |
| spelling | Kopanetz, I.E. Tolstolutskaya, G.D. Nikitin, A.V. Bilous, V.A. Kuprin, A.S. Ovcharenko, V.D. Vasilenko, R.L. 2017-01-19T20:09:23Z 2017-01-19T20:09:23Z 2015 The effect OF Cr, Cr-N and Cr-Ox coatings on deuterium retention and penetration in zirconium alloy Zr-1Nb / I.E. Kopanetz, G.D. Tolstolutskaya, A.V. Nikitin, V.A. Bilous, A.S. Kuprin, V.D. Ovcharenko, R.L. Vasilenko // Вопросы атомной науки и техники. — 2015. — № 5. — С. 81-86. — Бібліогр.: 16 назв. — англ. 1562-6016 https://nasplib.isofts.kiev.ua/handle/123456789/112288 669.296.004.0772 Depth distribution profiles of deuterium in zirconium alloy Zr-1Nb in initial state and with coatings Cr, CrN, and Cr₂O₃ after ion implantation with 15 keV/D⁺ at temperatures 350 °C to dose 1·10¹⁷ D/cm⁻² and deuterium plasma of glow discharge at room temperature are determined by the method of nuclear reactions. It is shown that in studied range of temperatures and concentrations of deuterium coatings CrN and Cr₂O₃ act as barrier and protect zirconium from interaction with hydrogen isotope. У вихідному сплаві цирконію і в сплаві з Cr-, CrN- и Cr₂O₃-покриттями методом ядерних реакцій виміряні профілі розподілу дейтерію, який імплантований з енергією 15 кеВ/D⁺ при температурі 350 °С до дози 1·10¹⁷ D/см⁻² і впроваджений при впливі плазми тліючого розряду. Показано, що в дослідженому інтервалі температур і концентрацій покриття CrN и Cr₂O₃ виступають бар'єром і захищають цирконій від взаємодії з ізотопом водню - дейтерієм. В исходном сплаве циркония и в сплаве с Cr-, CrN- и Cr₂O₃-покрытиями методом ядерных реакций измерены профили распределения дейтерия, имплантированного с энергией 15 кэВ/D⁺ при температуре 350 °С до дозы 1·10¹⁷ D/см⁻² и внедренного при воздействии плазмы тлеющего разряда. Показано, что в исследованном интервале температур и концентраций покрытия CrN и Cr₂O₃ выступают барьером и защищают цирконий от взаимодействия с изотопом водорода - дейтерием. en Національний науковий центр «Харківський фізико-технічний інститут» НАН України Вопросы атомной науки и техники Физика радиационных и ионно-плазменных технологий The effect OF Cr, Cr-N and Cr-Ox coatings on deuterium retention and penetration in zirconium alloy Zr-1Nb Вплив покриттів Cr, Cr-N та Cr-Ox на утримання і проникнення дейтерію в сплави цирконію Zr-1Nb Влияние покрытий Cr, Cr-N и Cr-Ox на удержание и проникновение дейтерия в сплавы циркония Zr-1Nb Article published earlier |
| spellingShingle | The effect OF Cr, Cr-N and Cr-Ox coatings on deuterium retention and penetration in zirconium alloy Zr-1Nb Kopanetz, I.E. Tolstolutskaya, G.D. Nikitin, A.V. Bilous, V.A. Kuprin, A.S. Ovcharenko, V.D. Vasilenko, R.L. Физика радиационных и ионно-плазменных технологий |
| title | The effect OF Cr, Cr-N and Cr-Ox coatings on deuterium retention and penetration in zirconium alloy Zr-1Nb |
| title_alt | Вплив покриттів Cr, Cr-N та Cr-Ox на утримання і проникнення дейтерію в сплави цирконію Zr-1Nb Влияние покрытий Cr, Cr-N и Cr-Ox на удержание и проникновение дейтерия в сплавы циркония Zr-1Nb |
| title_full | The effect OF Cr, Cr-N and Cr-Ox coatings on deuterium retention and penetration in zirconium alloy Zr-1Nb |
| title_fullStr | The effect OF Cr, Cr-N and Cr-Ox coatings on deuterium retention and penetration in zirconium alloy Zr-1Nb |
| title_full_unstemmed | The effect OF Cr, Cr-N and Cr-Ox coatings on deuterium retention and penetration in zirconium alloy Zr-1Nb |
| title_short | The effect OF Cr, Cr-N and Cr-Ox coatings on deuterium retention and penetration in zirconium alloy Zr-1Nb |
| title_sort | effect of cr, cr-n and cr-ox coatings on deuterium retention and penetration in zirconium alloy zr-1nb |
| topic | Физика радиационных и ионно-плазменных технологий |
| topic_facet | Физика радиационных и ионно-плазменных технологий |
| url | https://nasplib.isofts.kiev.ua/handle/123456789/112288 |
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