Assessment of the corrosion resistance of the main alternative materials for light water reactors tolerant fuel rod cladding
Basic materials for nuclear fuel rod claddings (Zr+1%Nb and E110 alloys), as well as alternative materials for tolerant fuel rod claddings (Cr18Ni10Тi steel and 42CrNiМo alloy), that are able to maximally prevent the development of severe accidents at nuclear power plants were tested in the high-tem...
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Національний науковий центр «Харківський фізико-технічний інститут» НАН України
2022
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| Zitieren: | Assessment of the corrosion resistance of the main alternative materials for light water reactors tolerant fuel rod cladding / V. Zuyok, R. Rud, M. Tretyakov, N. Rud, Y. Kushtym, I. Dykyy, I. Shevchenko, H. Rostova, V. Shtefan // Problems of Atomic Science and Technology. — 2022. — № 4. — С. 89-96. — Бібліогр.: 30 назв. — англ. |
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Digital Library of Periodicals of National Academy of Sciences of Ukraine| _version_ | 1859799509195816960 |
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| author | Zuyok, V. Rud, R. Tretyakov, M. Rud, N. Kushtym, Y. Dykyy, I. Shevchenko, I. Rostova, H. Shtefan, V. |
| author_facet | Zuyok, V. Rud, R. Tretyakov, M. Rud, N. Kushtym, Y. Dykyy, I. Shevchenko, I. Rostova, H. Shtefan, V. |
| citation_txt | Assessment of the corrosion resistance of the main alternative materials for light water reactors tolerant fuel rod cladding / V. Zuyok, R. Rud, M. Tretyakov, N. Rud, Y. Kushtym, I. Dykyy, I. Shevchenko, H. Rostova, V. Shtefan // Problems of Atomic Science and Technology. — 2022. — № 4. — С. 89-96. — Бібліогр.: 30 назв. — англ. |
| collection | DSpace DC |
| container_title | Вопросы атомной науки и техники |
| description | Basic materials for nuclear fuel rod claddings (Zr+1%Nb and E110 alloys), as well as alternative materials for tolerant fuel rod claddings (Cr18Ni10Тi steel and 42CrNiМo alloy), that are able to maximally prevent the development of severe accidents at nuclear power plants were tested in the high-temperature water vapor environment. A comparative analysis of the corrosion resistance of these materials is presented, as well as the results of similar tests by the world’s leading scientists. Samples of 42CrNiМo alloy revealed the highest corrosion resistance at high temperatures in a water vapor environment among the alternative materials for the fuel rod cladding considered in the study. The corrosion resistance of this alloy at a temperature of 1200 °C is approximately 40 times higher than that of Cr18Ni10Тi steel and E110 alloy. The high-temperature corrosion rate of the 42CrNiМo alloy is comparable to the corrosion rate of the Fechral alloy. The hydrogen that would be released during the oxidation of the 42CrNiМo alloy claddings would be almost forty times less compared to the zirconium alloy under the conditions of severe design accidents associated with overheating of the core.
Проведено високотемпературні дослідження в середовищі водяної пари базових матеріалів оболонок ядерного палива (сплави Zr+1%Nb та Е110), а також альтернативних матеріалів оболонок толерантного палива (сталі Х18Н10Т та 42ХНМ), які здатні максимально перешкоджати розвитку важких аварій на АЕС. Представлено порівняльний аналіз корозійної стійкості цих матеріалів, а також результати подібних випробувань світових провідних вчених. Із розглянутих у роботі альтернативних матеріалів оболонки твел найбільш високу корозійну стійкість при високих температурах у середовищі водяної пари показали зразки сплаву 42ХНМ. Корозійна стійкість цього сплаву при температурі 1200 °С приблизно в 40 разів вища, ніж сталі Х18Н10Т та сплаву Е110. Швидкість високотемпературної корозії сплаву 42ХНМ співставна зі швидкістю корозії сплаву фехраль. В умовах максимальних проектних аварій, пов’язаних з перегрівом активної зони, кількість водню, який виділиться при окисненні оболонок, виготовлених зі сплаву 42ХНМ, буде майже в 40 разів менше в порівнянні з цирконієвим сплавом.
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| first_indexed | 2025-12-07T15:12:02Z |
| format | Article |
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ISSN 1562-6016. ВАНТ. 2022. №4(140) 89
https://doi.org/10.46813/2022-140-089
UDC 621.039
ASSESSMENT OF THE CORROSION RESISTANCE OF THE MAIN
ALTERNATIVE MATERIALS FOR LIGHT WATER REACTORS
TOLERANT FUEL ROD CLADDING
Valeriy Zuyok1, Roman Rud1, Mykhaylo Tretyakov1, Nataliya Rud1, Yana Kushtym1,
Ivan Dykyy1, Igor Shevchenko1, Hanna Rostova1, Viktoriia Shtefan2
1National Science Center “Kharkov Institute of Physics and Technology”, Kharkiv, Ukraine;
2National Technical University “Kharkiv Polytechnic Institute”, Kharkiv, Ukraine
E-mail: valeriyz@kipt.kharkov.ua
Basic materials for nuclear fuel rod claddings (Zr+1%Nb and E110 alloys), as well as alternative materials for
tolerant fuel rod claddings (Cr18Ni10Тi steel and 42CrNiМo alloy), that are able to maximally prevent the
development of severe accidents at nuclear power plants were tested in the high-temperature water vapor environment.
A comparative analysis of the corrosion resistance of these materials is presented, as well as the results of similar tests
by the world's leading scientists. Samples of 42CrNiМo alloy revealed the highest corrosion resistance at high
temperatures in a water vapor environment among the alternative materials for the fuel rod cladding considered in the
study. The corrosion resistance of this alloy at a temperature of 1200 °C is approximately 40 times higher than that of
Cr18Ni10Тi steel and E110 alloy. The high-temperature corrosion rate of the 42CrNiМo alloy is comparable to the
corrosion rate of the Fechral alloy. The hydrogen that would be released during the oxidation of the 42CrNiМo alloy
claddings would be almost forty times less compared to the zirconium alloy under the conditions of severe design
accidents associated with overheating of the core.
INTRODUCTION
The Fukushima accident showed the special danger
of the steam-zirconium reaction and gave impetus to
R&D into the development of accident tolerant fuel
(ATF). Ensuring the long-term stability of light water
reactor fuel rod claddings under the design conditions
and severe accidents is an important and urgent task,
which is being solved by a large number of scientists
from all over the world. One of the ways to ensure long-
term stability, that is considered by the scientific
community, is to replace the zirconium alloy for the fuel
rod cladding with another, more corrosion-resistant
material with a low neutron absorption cross section,
which at high temperature oxidation will not result in the
formation of a large amount of explosive hydrogen and
the destruction of the cladding [1–3].
The ATF must be capable of operating both under
normal conditions and under loss of coolant conditions
according to the specification of the IAEA. Basing on
this, it can be argued that one of the most important
characteristics of the construction material of the fuel rod
cladding is its corrosion resistance, which should
maximally prevent the development of serious accidents
with loss of coolant.
The advantages of steel in comparison with zirconium
alloys are well-known: high corrosion resistance in
steam-water coolant, absence of steam-zirconium
reaction, experience of operation in various types of
reactors, including light water reactors, and the
availability of industrial technology for manufacturing
thin-walled weld-free pipes and components.
At the beginning of atomic energy era in the first
reactors of the Soviet design, steels Cr18Ni10Ti and
Cr15NiMo3B were used as materials for fuel rod
claddings. Austenitic steels and high-nickel alloys also
were used in foreign reactors at the first stages. However,
the major disadvantages of austenitic alloys, according to
a number of authors, are stress corrosion cracking (SCC)
as a result of radiation-induced depletion of grain
boundaries by chromium [4] and a high thermal neutron
capture cross section, which required either an increase
in enrichment or a decrease in the wall thickness of the
fuel rod cladding. Among the candidate materials for the
fuel rod cladding are corrosion-resistant alloys based on
iron – fechral alloys. SCC is not inherent to these
materials, but radiation embrittlement is observed. At
operating temperatures, the solid solution decomposes
with the formation of a chromium-enriched α-phase,
which is accelerated under irradiation [5].
At present, the development of ATF is a major
concern in the nuclear research fields in the present time.
The research concepts for enhanced ATF cladding
development consists of Mo-Zr cladding [6], cladding
coating [7, 8], iron-based alloy cladding [9, 10] and SiC
cladding [11].
Chromium-nickel alloy 42CrNiMo is one of the
promising alternative materials for fuel rod claddings.
This alloy possesses high strength and plasticity, high
corrosion resistance in various environments, high
radiation resistance, as well as structural and mechanical
stability under normal operating conditions of the
WWER reactor. The advantage of the 42CrNiMo alloy is
its long-term operation in the nuclear industry, where it
has established itself as a reliable material for various
nuclear power plants. This alloy is used for the
manufacturing of fuel rod claddings of transport reactors,
as well as RCCA rod claddings for WWER-1000
reactors.
There is no publicly available detailed description of
the 42CrNiMo alloy corrosion resistance due to the
specifics of its operation in transport nuclear power
reactors. Its implementation as a material for the RCCA
mailto:valeriyz@kipt.kharkov.ua
90 ISSN 1562-6016. ВАНТ. 2022. №4(140)
rod claddings, in contrast to the fuel rod claddings, does
not require substantiation of its operability in a LOCA-
type accidents.
The purpose of the study is to evaluate the corrosion
resistance of the main alternative zirconium alloy fuel rod
cladding materials in the water vapor environment for the
selection of the optimal construction material for the fuel
rod cladding of the tolerant fuel for light water reactors.
1. RESEARCH MATERIALS
AND METHODS
Zirconium alloy E110 cladding tubes manufactured
by TVEL LLC (Russia), that has been tested and certified
for WWER power reactors, were used as the base
material, to compare the obtained experimental results
with the results of similar studies of other alternative
materials.
The second base material were zirconium alloy
Zr+1%Nb thin-walled weld-free tubes manufactured in
Ukraine. The Zr+1%Nb alloy and the manufacturing
technology of cladding tubes at the SE “Zirkoniy” [12]
were developed to solve the problem of zirconium within
the framework of the program to create a nuclear fuel
cycle in Ukraine [13]. The alloy was obtained by the
technology of calciumthermic reduction of zirconium
from zirconium tetrafluoride and subsequent refining of
this metal by electron beam melting [14]. The content of
impurities and alloying element in alloy ingots after
remelting meet the requirements of TU 95.166-98 for
E110 alloy.
Thin-walled weld-free tubes manufactured of
Cr18Ni10Ti stainless steel and chrome-nickel alloy
42CrNiMo were selected as alternative materials for the
fuel rod cladding, that are similar in geometrical
parameters to the parameters of the WWER reactor fuel
rod cladding. The manufacturing of these tubes is
currently mastered by the Ukrainian enterprises
“OSKAR” LLC (Nikopol) and “Dniprovsky Special Pipe
Plant” LLC (Dnipropetrovsk region). For many years, the
enterprises have been supplying products of the 1st and
2nd safety classes for SE “NNEGC “Energoatom”. These
products are implemented in the equipment of all 15
nuclear power units of Ukrainian NPPs, both in the core
and in the 2nd and 3rd circuits.
The corrosion resistance of materials alternative to
zirconium alloy was evaluated basing on the results of
high-temperature tests at temperatures from 350 °C to
1200 °C in a water vapor environment in a tubular
furnace at atmospheric pressure. The maximum
isothermal exposure time was 1 h. Distilled water heated
to boiling temperature was used to obtain steam. Before
entering the tubular furnace, water vapor was
additionally heated to a temperature of 250…300 °C, for
that a certain section of the steam pipeline was equipped
with additional heater. The length of the uniform
temperature area in the furnace (working zone of the
furnace) was 500 mm. The initial temperature of the
sample was in the range from 100 °C to 300 °C. The
heating rate of the sample from the initial temperature to
1000 °C was more than 20 °C per second (the
temperature was reached in less than 35 s). The heating
rate from 1000 to 1200 °C exceeded 2 °C per second
(heating in less than 100 s).
2. RESEARCH RESULTS
2.1. HIGH-TEMPERATURE CORROSION
KINETICS OF ZIRCONIUM ALLOYS
Corrosion tests of fuel rod cladding samples
manufactured of zirconium alloy E110 and Ukrainian
alloy Zr+1%Nb are being carried out for a long time in
the NFC STE of the NSC KIPT. A large number of
articles are been devoted to the study of the high-
temperature corrosion kinetics of these alloys [15, 16].
The results of the study of the mass change kinetics of
E110 and Zr+1%Nb alloy samples in stationary tests in a
water vapor environment are given in articles [17–22].
This article summarizes the results of corrosion tests of
samples of the Ukrainian alloy Zr+1%Nb at temperatures
from 660 to 1200 °C when exposure time from 1 to 9 h
and compares them with the results of the E110 alloy
corrosion tests (Fig. 1).
The dependence of the average corrosion rate during
one hour on the test temperature of samples of both
zirconium alloys (E110 and Ukrainian Zr+1%Nb) in a
water vapor environment (Fig. 2) showed a low rate of
mass increase up to a temperature of 770 °C, that was
~ 114 mg/(dm2·h). With an increase in the test
temperature, the mass gain rate of the samples increases
sharply and at a temperature of 1200 °C in 1 h test it was
3600 mg/dm2 for the E110 alloy and 3230 mg/dm2 for the
Zr+1%Nb alloy. That is, the high-temperature corrosion
rate of the Ukrainian Zr+1%Nb alloy was somewhat
lower than the E110 alloy corrosion rate.
Fig. 1. Corrosion kinetics of zirconium alloy samples
in a water vapor environment
Fig. 2. The dependence of the zirconium alloy samples
average corrosion rate on the test temperature in a
water vapor environment
ISSN 1562-6016. ВАНТ. 2022. №4(140) 91
The corrosion tests results at high temperatures could
vary slightly depending on the rate at which the sample
is heated to a given temperature and the number of
thermal cycles the sample subjected before the desired
exposure time was reached. The mass change was even
higher and reached 4100 mg/dm2 for both alloys at
periodical weighing (after 5, 10, 15, and 60 min of
exposure) the same set of samples.
The appearance of the samples during the test is
summarized in (Fig. 3). The appearance of E110 and
Zr+1%Nb alloys samples was identical after all tests.
660 °С 770 °С 900 °С 1020 °С 1200 °С
Fig. 3. Appearance of zirconium alloys samples after tests in a water vapor environment
2.2. HIGH-TEMPERATURE CORROSION
KINETICS OF 08Cr18Ni10Ti STEEL
Studying of the corrosion resistance of 08Cr18Ni10Ti
steel at high temperatures in a water vapor environment
has been started relatively recently at the NFC STE NSC
KIPT [23, 24]. A much larger number of works was
previously devoted to studying the corrosion kinetics of
steels grades 06Cr18Ni10Ti, 08Cr18Ni10Ti, and
12Cr18Ni10Ti in model environments at the parameters
of the WWER-1000 primary coolant. Interest in this
study was initiated by the search for alternative materials
for nuclear fuel rod claddings resistant to accidents [25–
29].
Corrosion tests of 08Cr18Ni10Ti steel samples were
carried out in a water vapor environment for 1 h in the
temperature range from 350 to 1200 °C as part of this
study. Increasing the time of isothermal exposure results
in a mass gain of samples for all temperatures. The
corrosion kinetics of 08Cr18Ni10Ti steel samples at 1 h
testing in a water vapor environment in the temperature
range from 350 to 1200 °C is decaying (Fig. 4), i.e. the
curve can be characterized as a power-law dependence.
The dependence of the average corrosion rate for 1 h
on the test temperature of 08Cr18Ni10Ti steel samples in
water vapor (Fig. 5) reveals a low rate of mass gain for
the samples up to a temperature of 800 °C. At the same
time, the mass gain does not exceed 100 mg/dm2, a sharp
mass gain is observed at a temperature above 800 °C.
Mass gain for samples that were exposed for 1 h at a
temperature of 1200 °C was almost 4000 mg/dm2.
Fig. 4. Corrosion kinetics of 08Cr18Ni10Ti steel
samples in a water vapor environment
Fig. 5. Dependence of the average corrosion rate of
08Cr18Ni10Ti steel samples on the test temperature in
a water vapor environment
92 ISSN 1562-6016. ВАНТ. 2022. №4(140)
700 °С 900 °С 1000 °С 1100 °С 1200 °С
Fig. 6. Appearance of 08Cr18Ni10Ti steel samples after testing in a water vapor environment
The appearance of the surface changed during the test
from dark gray color over gray and brown to gray color
with a metallic luster after test at a temperature of
1200 °C (Fig. 6).
2.3. HIGH-TEMPERATURE CORROSION
KINETICS OF THE 42CrNiMo ALLOY
The corrosion tests results of 42CrNiMo samples in a
water vapor environment for 1 hour in the temperature
range from 350 to 1200 °С revealed that the corrosion
kinetics of this alloy is decaying (Fig. 7). This indicates
to the protective properties of the oxide film, formed
during corrosion testing in a water vapor environment.
The rate of mass gain increased with increasing the
test temperature, as evidenced by the dependence of the
average corrosion rate during 1 h on the test temperature
(Fig. 8). A characteristic feature of the corrosion
resistance of the 42CrNiMo alloy samples in the water
vapor environment is that the corrosion rate is much
lower compared to the Zr+1Nb alloy and the
08Cr18Ni10Ti steel. The dependence curve of the
average corrosion rate of the 42CrNiMo samples alloy is
similar to the curves for the Zr+1Nb alloy and the
08Cr18Ni10Ti steel. A sharp mass gain of the samples
was observed at a temperature above 800 °C, and at a
temperature of 1200 °C in 1 h of testing it was
120 mg/dm2.
The appearance of the surface changed from brown
over black and dark green to gray color at the end of the
test at a temperature of 1200 °C (Fig. 9).
Fig. 7. Corrosion kinetics of the 42CrNiMo alloy samples
in a water vapor environment
Fig. 8. Dependence of the average corrosion rate of
42CrNiMo alloy samples in 1 h on the test
temperature in a water vapor environment
ISSN 1562-6016. ВАНТ. 2022. №4(140) 93
700 °С 900 °С 1000 °С 1100 °С 1200 °С
Fig. 9. Appearance of 42CrNiMo alloy samples after testing in a water vapor environment
3. DISCUSSION OF RESULTS
The paper presents the research results of corrosion
resistance in the water vapor environment of the basic
materials for WWER nuclear fuel rod claddings and
alternative materials of tolerant fuel rod claddings.
Austenitic stainless steel Cr18Ni10Ti and chrome-nickel
alloy 42CrNiMo were tested as alternative materials.
These materials are able to maximally prevent the
development of severe accidents at nuclear power plants
according to the world community [1–3], and are
produced at Ukrainian enterprises.
The kinetics of the mass change of tube samples
manufactured of all studied materials is decaying (Figs.
1, 4, 7) and can be characterized by a power-law
dependence, that indicates the protective properties of
oxide films that are formed under high-temperature
corrosion testing in a water vapor environment.
High-temperature corrosion tests of tube samples
manufactured of 08Cr18Ni10Ti steel revealed higher
corrosion resistance, but up to temperatures of 1100 °C.
The corrosion rate increased at higher temperatures, and
at a temperature of 1200 °C it was comparable to the
corrosion rate of zirconium alloy E110 (Fig. 10), and the
mass gain was almost 4100 mg/dm2 after exposure for
about 1 h.
The high-temperature corrosion rate of the
42CrNiMo alloy samples was significantly lower than
that of the E110 alloy and stainless steel Cr18Ni10Ti (see
Fig. 10). Products manufactured of 42CrNiMo alloy
revealed high corrosion resistance even at a temperature
of 1200 °C. The corrosion resistance of the 42CrNiMo in
a water vapor environment at a temperature of 1200 °C
was approximately 40 times higher than that of the
Cr18Ni10Ti steel and the E110 alloy (see Fig. 10). There
is lack of information on the corrosion resistance of the
42CrNiMo alloy under core operating conditions due to
the specifics of this alloy implementation in nuclear
power reactors. In paper [30] it is stated that the
difference in the amount of material that has turned into
an oxide can reach 90 times. But the paper does not
specify the parameters of corrosion tests that can affect
the oxidation kinetics, such as the heating rate, the
corrosion environment (water vapor or air), the state of
the samples surface (mechanical, chemical,
electrochemical treatment). But the comparative data
obtained in this study do not contradict the literature data
given in [30] and confirm the significantly higher
corrosion resistance of the 42CrNiMo alloy compared to
the E110 alloy.
The question arises as to how much the corrosion
resistance of 42CrNiMo alloy tubes is higher compared
to other metal materials suitable for high-temperature
operation. High-temperature tests of Fechral alloy
samples were carried out for comparison, despite the fact
that this material was not in the form of tubes and that it
was not implemented in nuclear power industry at all.
Fechral alloy is the material for the manufacture of
heating elements of powerful electronic heating devices
and operates at temperatures up to 1400 °C due to its high
corrosion resistance in air at high temperature.
Fig. 11 shows the dependence of the average
corrosion rate for 1 h of the 42CrNiMo alloy tube
samples and industrially manufactured Fechral alloy
plates on the test temperature in a water vapor
environment. The high-temperature corrosion rate of the
42CrNiMo alloy was comparable to the corrosion rate of
Fig. 10. Dependence of the average corrosion rate of
Zr+1%Nb, Cr18Ni10Ti and 42CrNiMo samples on
the test temperature in a water vapor environment
94 ISSN 1562-6016. ВАНТ. 2022. №4(140)
the Fechral alloy basing on the obtained results. The mass
gain of both alloys was 100...105 mg/dm2.
This indicates that 42CrNiMo alloy tubes reveal the
highest corrosion resistance among metal materials,
manufactured in Ukraine. Therefore, this alloy can be
recommended for implementation as an alternative
material for rod claddings of tolerant fuel. But it should
be noted that the justification of this material operation in
the core of a light water reactor has great difficulties,
which are associated with a sharp change in mechanical
characteristics at high temperature and significant
parasitic capture of thermal neutrons (~ 21%). In order to
reduce the parasitic capture of thermal neutrons,
adaptation of claddings manufactured of this alloy for
operation in WWER is required, and consists in reducing
the wall thickness of the tube, if it does not result in a loss
of mechanical stability.
CONCLUSIONS
1. Basic materials for nuclear fuel rod claddings
(Zr+1%Nb and E110 alloys), as well as alternative
materials for tolerant fuel rod claddings (Cr18Ni10Тi
steel and 42CrNiМo alloy), that are able to maximally
prevent the development of severe accidents at nuclear
power plants were tested in the high-temperature water
vapor environment. A comparative analysis of the
corrosion resistance of these materials is presented, as
well as the results of similar tests by the world's leading
scientists.
2. An increase in the corrosion rate of zirconium
alloys of both brands at a test temperature above
700...750 °С in a water vapor environment was observed.
The high-temperature oxidation kinetics of the Ukrainian
Zr+1%Nb alloy and the E110 alloy have a similar
character, with a difference of up to 40% in the
temperature range of 900…1000 °C, probably related to
the higher oxygen content in the Zr+1%Nb alloy. Testing
at a temperature of 1200 °C resulted in a mass gain of
both zirconium alloys, that was almost 4100 mg/dm2
after 1 h exposure.
3. The mass change kinetics of 08Cr18Ni10Тi
steel samples is decaying and can be characterized by a
power-law dependence, which indicates the protective
properties of oxide films. The dependence of the average
corrosion rate in 1 h on the test temperature of the steel
samples in water vapor revealed a low rate of mass gain
up to a temperature of 700 °C. A sharp mass gain was
observed at a temperature above 800 °C, and after 1 hour
exposure at a temperature of 1200 °C it was almost
4000 mg/dm2.
4. The mass change kinetics of chromium-nickel
alloy 42CrNiМo samples is decaying and characterized
by a power-law dependence. A sharp mass gain rate with
an increase in the test temperature to 1200 °C was not
observed. After 1 h exposure at a temperature of 1200 °C
the mass gain was only 105 mg/dm2.
5. Samples of 42CrNiМo alloy revealed the
highest corrosion resistance at high temperatures in a
water vapor environment among the alternative materials
for the fuel rod cladding considered in the study. The
corrosion resistance of this alloy at a temperature of
1200 °C is approximately 40 times higher than that of
Cr18Ni10Тi steel and E110 alloy. The high-temperature
corrosion rate of the 42CrNiМo alloy is comparable to
the corrosion rate of the Fechral alloy. The hydrogen that
would be released during the oxidation of the 42CrNiМo
alloy claddings would be almost forty times less
compared to the zirconium alloy under the conditions of
severe design accidents associated with overheating of
the core.
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Article received 17.07.2022
96 ISSN 1562-6016. ВАНТ. 2022. №4(140)
ОЦІНКА КОРОЗІЙНОЇ СТІЙКОСТІ ОСНОВНИХ АЛЬТЕРНАТИВНИХ МАТЕРІАЛІВ
ОБОЛОНКИ ТОЛЕРАНТНОГО ПАЛИВА ЛЕГКОВОДНИХ РЕАКТОРІВ
Валерій Зуйок, Роман Рудь, Михайло Трет’яков, Наталія Рудь, Яна Куштим, Іван Дикий,
Ігор Шевченко, Ганна Ростова, Вікторія Штефан
Проведено високотемпературні дослідження в середовищі водяної пари базових матеріалів оболонок
ядерного палива (сплави Zr+1%Nb та Е110), а також альтернативних матеріалів оболонок толерантного
палива (сталі Х18Н10Т та 42ХНМ), які здатні максимально перешкоджати розвитку важких аварій на АЕС.
Представлено порівняльний аналіз корозійної стійкості цих матеріалів, а також результати подібних
випробувань світових провідних вчених. Із розглянутих у роботі альтернативних матеріалів оболонки твел
найбільш високу корозійну стійкість при високих температурах у середовищі водяної пари показали зразки
сплаву 42ХНМ. Корозійна стійкість цього сплаву при температурі 1200 °С приблизно в 40 разів вища, ніж
сталі Х18Н10Т та сплаву Е110. Швидкість високотемпературної корозії сплаву 42ХНМ співставна зі
швидкістю корозії сплаву фехраль. В умовах максимальних проектних аварій, пов’язаних з перегрівом
активної зони, кількість водню, який виділиться при окисненні оболонок, виготовлених зі сплаву 42ХНМ,
буде майже в 40 разів менше в порівнянні з цирконієвим сплавом.
|
| id | nasplib_isofts_kiev_ua-123456789-195413 |
| institution | Digital Library of Periodicals of National Academy of Sciences of Ukraine |
| issn | 1562-6016 |
| language | English |
| last_indexed | 2025-12-07T15:12:02Z |
| publishDate | 2022 |
| publisher | Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
| record_format | dspace |
| spelling | Zuyok, V. Rud, R. Tretyakov, M. Rud, N. Kushtym, Y. Dykyy, I. Shevchenko, I. Rostova, H. Shtefan, V. 2023-12-05T09:57:55Z 2023-12-05T09:57:55Z 2022 Assessment of the corrosion resistance of the main alternative materials for light water reactors tolerant fuel rod cladding / V. Zuyok, R. Rud, M. Tretyakov, N. Rud, Y. Kushtym, I. Dykyy, I. Shevchenko, H. Rostova, V. Shtefan // Problems of Atomic Science and Technology. — 2022. — № 4. — С. 89-96. — Бібліогр.: 30 назв. — англ. 1562-6016 DOI: https://doi.org/10.46813/2022-140-089 https://nasplib.isofts.kiev.ua/handle/123456789/195413 621.039 Basic materials for nuclear fuel rod claddings (Zr+1%Nb and E110 alloys), as well as alternative materials for tolerant fuel rod claddings (Cr18Ni10Тi steel and 42CrNiМo alloy), that are able to maximally prevent the development of severe accidents at nuclear power plants were tested in the high-temperature water vapor environment. A comparative analysis of the corrosion resistance of these materials is presented, as well as the results of similar tests by the world’s leading scientists. Samples of 42CrNiМo alloy revealed the highest corrosion resistance at high temperatures in a water vapor environment among the alternative materials for the fuel rod cladding considered in the study. The corrosion resistance of this alloy at a temperature of 1200 °C is approximately 40 times higher than that of Cr18Ni10Тi steel and E110 alloy. The high-temperature corrosion rate of the 42CrNiМo alloy is comparable to the corrosion rate of the Fechral alloy. The hydrogen that would be released during the oxidation of the 42CrNiМo alloy claddings would be almost forty times less compared to the zirconium alloy under the conditions of severe design accidents associated with overheating of the core. Проведено високотемпературні дослідження в середовищі водяної пари базових матеріалів оболонок ядерного палива (сплави Zr+1%Nb та Е110), а також альтернативних матеріалів оболонок толерантного палива (сталі Х18Н10Т та 42ХНМ), які здатні максимально перешкоджати розвитку важких аварій на АЕС. Представлено порівняльний аналіз корозійної стійкості цих матеріалів, а також результати подібних випробувань світових провідних вчених. Із розглянутих у роботі альтернативних матеріалів оболонки твел найбільш високу корозійну стійкість при високих температурах у середовищі водяної пари показали зразки сплаву 42ХНМ. Корозійна стійкість цього сплаву при температурі 1200 °С приблизно в 40 разів вища, ніж сталі Х18Н10Т та сплаву Е110. Швидкість високотемпературної корозії сплаву 42ХНМ співставна зі швидкістю корозії сплаву фехраль. В умовах максимальних проектних аварій, пов’язаних з перегрівом активної зони, кількість водню, який виділиться при окисненні оболонок, виготовлених зі сплаву 42ХНМ, буде майже в 40 разів менше в порівнянні з цирконієвим сплавом. en Національний науковий центр «Харківський фізико-технічний інститут» НАН України Вопросы атомной науки и техники Thermal and fast reactor materials Assessment of the corrosion resistance of the main alternative materials for light water reactors tolerant fuel rod cladding Оцінка корозійної стійкості основних альтернативних матеріалів оболонки толерантного палива легководних реакторів Article published earlier |
| spellingShingle | Assessment of the corrosion resistance of the main alternative materials for light water reactors tolerant fuel rod cladding Zuyok, V. Rud, R. Tretyakov, M. Rud, N. Kushtym, Y. Dykyy, I. Shevchenko, I. Rostova, H. Shtefan, V. Thermal and fast reactor materials |
| title | Assessment of the corrosion resistance of the main alternative materials for light water reactors tolerant fuel rod cladding |
| title_alt | Оцінка корозійної стійкості основних альтернативних матеріалів оболонки толерантного палива легководних реакторів |
| title_full | Assessment of the corrosion resistance of the main alternative materials for light water reactors tolerant fuel rod cladding |
| title_fullStr | Assessment of the corrosion resistance of the main alternative materials for light water reactors tolerant fuel rod cladding |
| title_full_unstemmed | Assessment of the corrosion resistance of the main alternative materials for light water reactors tolerant fuel rod cladding |
| title_short | Assessment of the corrosion resistance of the main alternative materials for light water reactors tolerant fuel rod cladding |
| title_sort | assessment of the corrosion resistance of the main alternative materials for light water reactors tolerant fuel rod cladding |
| topic | Thermal and fast reactor materials |
| topic_facet | Thermal and fast reactor materials |
| url | https://nasplib.isofts.kiev.ua/handle/123456789/195413 |
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