Electron irradiation test facility for irradiation of structural materials in conditions of molten salt reactor
A new device, Electron Irradiation Test Facility (EITF), has been created at electron linear accelerator Linac-10 at Accelerator R&D Complex affiliated with NSC KIPT. This facility allows to carry on studies on corrosion resistance of differently shaped samples of the Hastelloy type alloys i...
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| Опубліковано в: : | Вопросы атомной науки и техники |
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| Дата: | 2005 |
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Національний науковий центр «Харківський фізико-технічний інститут» НАН України
2005
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| Назва журналу: | Digital Library of Periodicals of National Academy of Sciences of Ukraine |
| Цитувати: | Electron irradiation test facility for irradiation of structural materials in conditions of molten salt reactor / V.M. Azhazha, A.S. Bakai, I.V. Gurin, A.M. Dovbnya, M.V. Demidov, A.I. Zykov, E.S. Zlunitsyn, S.D. Lavrynenko, L.K. Myakushko, O.A. Repikhov, O.V. Torgovkin,B.M. Shirokov, B.I. Shramenko // Вопросы атомной науки и техники. — 2005. — № 4. — С. 20-23. — Бібліогр.: 1 назв. — англ. |
Репозитарії
Digital Library of Periodicals of National Academy of Sciences of Ukraine| _version_ | 1860004948694007808 |
|---|---|
| author | Azhazha, V.M. Bakai, A.S. Gurin, I.V. Dovbnya, A.M. Demidov, M.V. Zykov, A.I. Zlunitsyn, E.S. Lavrynenko, S.D. Myakushko, L.K. Repikhov, O.A. Torgovkin, O.V. Shirokov, B.M. Shramenko, B.I. |
| author_facet | Azhazha, V.M. Bakai, A.S. Gurin, I.V. Dovbnya, A.M. Demidov, M.V. Zykov, A.I. Zlunitsyn, E.S. Lavrynenko, S.D. Myakushko, L.K. Repikhov, O.A. Torgovkin, O.V. Shirokov, B.M. Shramenko, B.I. |
| citation_txt | Electron irradiation test facility for irradiation of structural materials in conditions of molten salt reactor / V.M. Azhazha, A.S. Bakai, I.V. Gurin, A.M. Dovbnya, M.V. Demidov, A.I. Zykov, E.S. Zlunitsyn, S.D. Lavrynenko, L.K. Myakushko, O.A. Repikhov, O.V. Torgovkin,B.M. Shirokov, B.I. Shramenko // Вопросы атомной науки и техники. — 2005. — № 4. — С. 20-23. — Бібліогр.: 1 назв. — англ. |
| collection | DSpace DC |
| container_title | Вопросы атомной науки и техники |
| description | A new device, Electron Irradiation Test Facility (EITF), has been created at electron linear accelerator Linac-10 at Accelerator R&D Complex affiliated with NSC KIPT. This facility allows to carry on studies on corrosion resistance of differently shaped samples of the Hastelloy type alloys in the melt of zirconium and sodium fluoride salts at high temperature. A container assembly (CA) that held samples was irradiated for 700 hours in the radiation field of electron beam with the energy ∼10 MeV and average current ∼500 microAmps (power∼5 kW ). The CA consisting of 16 containers (made of a carbon-carbon composite) that were loaded with research samples of Hastelloy alloys in the melt of the salts ZrF₄ и NaF was placed in air-tight protective shell made of stainless steel. During the irradiation, the CA was placed in argon atmosphere. The CA temperature was monitored with three thermocouples. Over the entire length of the irradiation process the stationary temperature regime was provided: 650°С ± 15°С.
На лінійному прискорювачі електронів ЛП−10 НДК «Прискорювач» ННЦ ХФТІ створено установку “Стенд для радіаційних випробувань”, яка дозволяє проводити дослідження корозійної стійкості зразків різних модифікацій сплавів типу “хастелой ”в разплаві фторидних солей цирконію та натрію при високій температурі. У радіаційному полі пучка електронів з енергією ∼10 МеВ та среднім струмом ∼500 мкА (потужністю ∼5 кВт ) впродовж 700 годин проведено опромінення збірки контейнерів з досліджуваними зразками. Збірку з 16 контейнерів (з вуглець-вугецевого композиту), заповнених зразками “хастелою”в расплаві солей ZrF₄ та NaF, розміщено в герметичній захистній оболонці з нержавіючої сталі. Збірка при опроміненні знаходилась в атмосфері аргону. Температура збірки контролювалась трьома термопарами.. Впродовж процесу опромінення підтримувався стаціонарний температурний режим: (650 ± 15°С).
На линейном ускорителе электронов ЛУ-10 НИК «Ускоритель» ННЦ ХФТИ создана установка “Стенд для радиационных испытаний”, позволяющая проводить исследования коррозионной стойкости образцов различных модификаций сплавов типа “хастеллой ”в расплаве фторидных солей циркония и натрия при высокой температуре.В радиационном поле пучка электронов с энергией ∼10 МэВ и средним током ∼500 мкА (мощностью ∼5 кВт ) в течение 700 ч проведено облучение сборки контейнеров с образцами. Сборка из 16 контейнеров (из углерод-углеродного композита), заполненных исследуемыми образцами “хастелоя”в расплаве солей ZrF₄ и NaF, помещалась в герметичную защитную оболочку из нержавеющей стали. Сборка при облучении находилась в атмосфере аргона. Температура ее контролировалась тремя термопарами. На протяжении всего процесса облучения обеспечивался стационарный температурный режим (650 ± 15)°С.
|
| first_indexed | 2025-12-07T16:38:26Z |
| format | Article |
| fulltext |
PACS:41.60.
ELECTRON IRRADIATION TEST FACILITY FOR IRRADIATION
OF STRUCTURAL MATERIALS IN CONDITIONS OF MOLTEN SALT
REACTOR
V.M. Azhazha, O.S. Bakai, I.V. Gurin, A.M. Dovbnya, M.V. Demidov, A.I. Zykov, E.S. Zlunit
syn, S.D. Lavrynenko, L.K. Myakushko, O.A. Repikhov, O.V. Torgovkin, B.M. Shirokov,
B.I. Shramenko
National Science Center “Kharkiv Institute of Physics and Technology”
1 Akademichna str., 61108, Kharkiv, Ukraine
E-mail: bshram@kipt.kharkov.ua
A new device, Electron Irradiation Test Facility (EITF), has been created at electron linear accelerator Linac-10
at Accelerator R&D Complex affiliated with NSC KIPT. This facility allows to carry on studies on corrosion resis
tance of differently shaped samples of the Hastelloy type alloys in the melt of zirconium and sodium fluoride salts at
high temperature. A container assembly (CA) that held samples was irradiated for 700 hours in the radiation field of
electron beam with the energy ∼10 MeV and average current ∼500 microAmps (power∼5 kW ). The CA consisting
of 16 containers (made of a carbon-carbon composite) that were loaded with research samples of Hastelloy alloys in
the melt of the salts ZrF4 и NaF was placed in air-tight protective shell made of stainless steel. During the irradia
tion, the CA was placed in argon atmosphere. The CA temperature was monitored with three thermocouples. Over
the entire length of the irradiation process the stationary temperature regime was provided: 650оС ± 15оС.
INTRODUCTION
Alongside with the economic benefits of escalation
of the atomic energy production, unfortunately, we face
a growing menace to the environment on account of ac
cumulation of nuclides with long half-lives, including
such nuclides that can well be used for nuclear weapons
production. The crucial factor in resolution of those
problems would be to employ molten-salt reactors
(MSR) with metallic heat carriers that provide for trans
mutation of the long-lived nuclides into short-lived,
eliminating thereby the tangible threat of catastrophic
stockpiling of radioactive waste. At the operation tem
peratures 650-800 оС, the corrosive influence of molten-
salt blanket and metallic heat carriers on the structural
materials under the conditions of irradiation is known
but a little, the prior reactor materials experience being
of little help, since it concerns the reactors of quite dif
ferent types. With this observation in mind, the chal
lenge of development and testing of the structural mate
rials for the high-temperature reactors employing the
metallic heat carriers and MSRs is of extreme impor
tance to those countries that are oriented to utilization of
the atomic energy.
Creation of novel promising, radiation-resistant
structural materials for atomic reactors of the new gen
eration is intertwined with the necessity to study the be
havior of those materials in the conditions that are close
to existing in the reactor core at Т≅650о С. These condi
tions were simulated via electron beam irradiation of the
CA containing samples of the structural materials.
The EITF has been built at NSC KIPT Linac-10, de
signed to sustain long-duration tests of the structural
materials in the radiation conditions that are very close
to those inside the MSR. To provide for the necessary
parameters of the radiation field of irradiation, the elec
tron beam with the energy ∼10 MeV and power output∼
5 kW was used. A peculiar characteristic of this ap
proach to simulation of the conditions of MSR was the
fact that heating of the CA up to the required tempera
ture Т=650оС±15оС was performed by electron beam
itself owing to the electron ionization losses in the car
bon containers that were filled up with research samples
of Hastelloy type alloys and melt of the fluoride salts
ZrF4 and NaF.
The radiation control over irradiated materials was
implemented, using the industrial type dosimeter “ДБГ-
01Н-№ 1519”, while the identification of radioactive
nuclides in irradiated materials and prediction about
their post-irradiation remnant activity vs. time were
done on the basis of measurement-takings of gamma-
spectra, using a γ-spectrometer of a semiconductor de
tector of the type “ДГЛК-100 В.”
EITF CONFIGURATION AT LINAC-10
In the result of analysis of technical capabilities of
various high-power technological accelerators found at
NSC-KIPT Accelerator R&D Complex (EPOS, KUT,
KUT-20 and Linac-10) the final choice was made in fa
vor of Linac-10.
This was made because of the following reasons:
wide limits of the regulation of the average current val
ue of electrons and energy at the peak of the spectrum;
feasibility of controlling the irradiation field dimensions
in accordance with the size of the input window in the
CA protective shell. The subsequent studies reaffirmed
the correctness of this choice.
The preliminary workouts of the necessary irradia
tion regime on CA mockups, an individual container
filled up with Hastelloy type samples and fluoride salt
melt and on the CA itself displayed the operability of
the EITF, including the temperature measurement sys
tem. These tests also allowed to predict the remnant ra
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ВОПРОСЫ АТОМНОЙ НАУКИ И ТЕХНИКИ. 2005. №.4.
Серия: Физика радиационных повреждений и радиационное материаловедение (87), с. 20-23.
20
dioactivity value of CA components after the long-dura
tion irradiation.
The EITF was installed at the linac-10 output
(downstream the exit foil), being an autonomous system
designed to operate for very long times (1,000…
1,500 h) irradiating with electrons the CAs that hold
samples of the structural materials.
A general scheme of the EITF setup at the linac-10
output, emphasizing the functional units, is given in
Fig. 1.
T3
T2
T1
VP VP
NT M
M
R
V1
V2
RV
V3
VC
S EFMA
PBA
LINAC-10
Ar
VL
Fig. 1. EITF for simulative testing of structural materi
als at Linac-10
LINAC-10 – Linear electron accelerator operable at the
energy 10 MeV (ЛУЭ – 10); МА – Magnetic analyzer;
S – Beam scanner; EF – Exit foi ; РВА – Protective CA
shell; VC – Vacuum connector for thermocouples;
VP – Vacuum pump-valve; М – Manovacuum-meter; Ar
– Vessel (with argon); R – Pressure regulator;
RV – Damping volume (rubber cushion); VL – Vacuum
lamp; NT – Nitrogen trap
The electron beam was swept with the scanner (S) in
the vertical, and it corresponded to the size of the pro
tective CA shell window at a distance of 850 mm from
the exit foil (EF). Inside the protective shell, there was
the CA made of a carbon-carbon composite.
The manifold that was used for remote filling of the
protective shell with argon was connected with the high-
pressure vessel (Ar) and equipped with the damping
volume (RV), “oxygen cushion” with the capacity 75 l,
the manovacuum-metric detector (M) and two vacuum
pumps (VP) with the nitrogen traps (NT). The airtight
protective shell allowed to conduct the radiation tests of
containers in argon atmosphere. The heating of the CA
up to the required temperature (650±15)оС was made di
rectly with the electron beam itself owing to the electron
ionization losses in the containers.
The temperature control of the CA was exercised us
ing three thermocouples of the C-K (chromel-kapel)
type: Т1 , Т2 and T3.
Fig. 2 shows in more detail the layout of the CA in
its protective shell.
The CA (7) is made up of 16 individual containers
made of a carbon-carbon composite. The containers are
filled up with Hastelloy samples of various modifica
tions in the salt melt of zirconium and sodium fluorides
ZrF4 and NаF.
The containers with the dimensions 40х40х50 mm3
are brought together in common assembly 80 mm wide
and 400 mm tall, placed in the airtight protective shell
made of stainless steel (1) which is water-cooled, with
the thin input window, being additionally cooled with
air flow.
In the upper- and lowermost parts of the assembly,
the gas getters (6) abut on the containers, which are a set
of thin titanium plates placed in the carbon container
with openings. The vacuum pumping of the entire EITF
with its subsequent filling with argon is made through
the inlet 4.
Fig. 2. Container-assembly in its protective shell
1 – Airtight protective shell; 2 – Input window; 3 –
Catch; 4 – Flange for vacuum pumping and argon fill
ing; 5 – Inlet for thermocouples Т1 – Т3; 6 – Getter ( Тi )
; 7 – Container-assembly made of carbon-carbon com
posite material; 8 – Heat insulating pillars
To take off the heat ≅ 5 kW, the water-cooling of the
shell was used. An additional cooling of the assembly
was made via air flow through the industrial air vent de
vice of the type “Ц4–70 № 2,5” with the throughput ca
pacity 900 m3/h, which operated through three air con
duits with slotted nozzles of a custom configuration,
two of which were used for blowing the protective shell
from two directions in its rear lateral zones, and one for
blowing the protective shell input window foil.
In this way, the EITF positioned at the output of
Linac-10 complete with the airtight protective shell and
cooling and temperature measurement systems allowed
for the simulative radiation via irradiation of containers
that hold samples of the structural materials in argon at
mosphere.
PRODUCTION OF NECESSARY RADIATION
FIELD AT LINAC-10
The electron beam was swept with the scanner in the
vertical over 400 mm (±200 mm off-center). The beam
transverse dimensions (in the horizontal) ≅ 100 mm (±
50 mm off-center) were accounted for by the process of
electron scattering at the exit (made of titanium) and
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ВОПРОСЫ АТОМНОЙ НАУКИ И ТЕХНИКИ. 2005. №.4.
Серия: Физика радиационных повреждений и радиационное материаловедение (87), с. 20-23.
21
protective (made of aluminum) foils of the scanner vac
uum chamber. In this way, at a distance 850 mm from
the exit foil, the electron beam looked like a strip 100
mm wide and 400 mm tall. Those beam dimensions cor
responded to the input window size of the CA protective
shell. To prevent the edge effects on bulky lateral
fringes of the input window, a collimator mask made of
aluminum with the dimensions 80х400 мм2 was in
stalled in front of the protective shell input window in
exact correspondence with the container assembly size.
At Linac-10, the average accelerated beam current
can be adjusted within the limits from (Iav)maх=1000 mi
croAmps to (Iav)min ≅1 microAmp. In order to avoid the
exit foil overheating, a long work with the current
~1000 microAmps is undesirable. The operation value
of the current is (Iav)=850 microАmps. Operation with
the concentrated beam (unscanned) is allowable within
the limits (Iav)=100 microАmps. Owing to the summa
tion of microwave power from two klystrons and their
excitation from the stable driving generator (DG),
Linac-10 allows for a smooth adjustment of the acceler
ator microwave power within broad limits and, respec
tively, average beam energy and current. The precision
energy adjustment can be done via input phasing of one
of the klystrons. This feature turns into an enormous
merit during running of the physical experiments and
caused the choice of Linac-10 to carry out the present
experimental work. The typical beam energy spectrum
of Linac-10 is shown in Fig. 3.
9 9,25 9,5 9,75 10 10,25 10,5 10,75 11 11,25 11,5 11,75 12
0
0,25
0,5
0,75
1
Spectrum of electrons
E, MeV
I /
I
m
ax
Fig. 3. Electron beam energy spectrum at Linac-10
With a decreasing of the microwave power input
into the accelerator, the main spectrum peak energy de
creases, while the spectral region near this peak shifts
toward smaller energies as a single whole without
changing the form of the spectrum. The measurements
taken of the spectra in various regimes of accelerator
operation permit to count on energy adjustment of the
main spectrum peak from 10 MeV to 7.5 MeV. This sit
uation secures the operation mode choice with the ener
gy below the threshold of the photonuclear reactions (γ
,n) and (γ,р) on irradiated items. The CA irradiation
with electrons was made at the following operation
mode of Linac-10:
Linac-10:
Spectrum peak electron energy – 9.6 MeV
Total average beam current – 520 microАmps
Repetition (group) rate – 150 Hz
Effective irradiation area – 80 х 400 mm2
Irradiation duration – 700 hours
Fluence ≅ 1019 e/cm2
PROLONGED IRRADIATION OF SAMPLES
OF STRUCTURAL MATERIALS
AND TEMPERATURE REGIME OF CA
IN THE PROCESS OF IRRADIATION
The challenging problem in the initial stage of this
research was to provide for the conditions of continuous
and prolonged (for 700 h) irradiation with electrons of
the CA, while keeping the CA temperature within the
limits of (650оС ± 20)оС in compliance with the Techni
cal Irradiation Assignment. The CA temperature control
was maintained with three thermocouples Т1 ÷ Т3 (Fig.
2) of C-K (chromel-kapel) type that have low sensitivity
for irradiation with gamma-quanta and provide for tem
perature measurements up to 800 оС. The temperature
measurements were taken using the multi-channel trans
ducer of the type “Ш 711/1И” with the accuracy ±
0,5оС.
The adjustment of assigned irradiation temperature
regime was done by selection of the accelerator beam
current that was continuously monitored and kept at the
assigned level. In the course of the entire irradiation run,
700 hours, the registration of temperature readings from
all three thermocouples was done every 15 to 20 min
utes. In this way, the CA total temperature irradiation
regime is depicted as an array of measurements consist
ing of ≅4,000 dots.
Fig. 4 presents the results of these measurements in
the form of a sampling (out of the total data array) of
700 dots per each thermocouple -Т1, Т2 and Т3 .
0 100 200 300 400 500 600 700
530
540
550
560
570
580
590
600
610
620
630
640
650
660
670
680
T
e
m
p
e
ra
tu
re
,
o C
Time, h
(Т3)
(Т2)
(Т1)
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ВОПРОСЫ АТОМНОЙ НАУКИ И ТЕХНИКИ. 2005. №.4.
Серия: Физика радиационных повреждений и радиационное материаловедение (87), с. 20-23.
22
Fig. 4. Container assembly temperature regime during irradiation for 700 hours
(The dots Т1, Т2,and Т3 stand for readings from the three thermocouples)
One can see from Fig. 4 that the highest temperature
was in the center of the CA (Т2) and its upper part,
while the lowest, in the lower part of the assembly (Т1),
but these values do not transgress the limits stipulated in
the Technical Assignment 650 оС ± 20 оС.
The dots indicating such temperature that transgress
es the above limits (predominantly for Т1) correspond to
short-duration (minutes) stoppages of the accelerator ac
counted for by intervention of the high-power electron
beam interrupter systems for various reasons that were
not caused directly by the operation of the EITF.
The average temperature value Т(AV) and standard
deviation (STD) were chosen over samplings of the 700
dots for each thermocouple, using the program EXCEL
5.0.
Т1 (AV) = 636.8 оС ; STD = 5.6 оС
Т2 (AV) = 663.4 оС; STD = 6.56 оС
Т3(AV) = 657.6 оС; STD = 7.0 оС
Accordingly, the average CA temperature for 700
hours was 652.6 C with the deviation alley not exceed
ing the deviations from the average temperature in ac
cordance with the requirements of Technical Irradiation
Assignment: (650 ± 20)оС.
For 700 hours of the irradiation of the CA the flu
ence was .≅ 1019 e/cm2.
The radiation control over irradiated materials was
exerted, using the industrial dosimeter of the type
“ДБГ-01Н-№ 1519”, while the determination of specif
ic activity of the nuclides in irradiated materials [1] and
prediction of the behavior of their post-irradiation rem
nant activity were made on the basis of the measure
ments of gamma-spectra with the aid of a γ-spectrome
ter with a semiconductor detector of the type “ДГЛК-
100 В”.
CONCLUSIONS
1. The Electron Irradiation Test Facility (EITF) has
been created at Linac-10 at Accelerator R&D Complex
affiliated with NSC KIPT. A technology has been per
fected for a long-duration irradiation with electron flux
es of samples of the structural materials in such condi
tions that are close to those existing in the reactor blan
ket.
2. A technique has been developed for controlled ra
diation and temperature irradiation regimes in argon at
mosphere of the Container Assembly (CA) made of a
carbon-carbon composite material (filled up with
Hastelloy type samples in the melt of fluoride salts of
ZrF4 and NaF), and the CA was irradiated with electron
beam with the power output about 5kW for 700 hours at
the temperature Т= (650 ±15) оС.
3.The experience of radiation tests gained to date,
using high-power electron beams, concerning the struc
tural materials in the conditions that are close to those
existing in the reactor blanket, shall be employed in fur
ther R&D on the structural materials for next-generation
reactors.
The research was supported in part by STCU,
Project # 294.
REFERENCES
A.N. Dovbnya, N.P. Dicky, O.V. Nemashkalo, A.I. Tu
tubalin, V.L. Uhvarov, A.G. Shepelev, B.I. Shramenko,
L.D. Yurchenko. Current status of the problem of nu
clide production for various purposes at accelerators and
reactors //Kharkov University bulletin. 2004, #619, p.
63.
СТЕНД ДЛЯ РАДИАЦИОННЫХ ИСПЫТАНИЙ
КОНСТРУКЦИОННЫХ МАТЕРИАЛОВ В УСЛОВИЯХ СОЛЕВОГО РЕАКТОРА
В.М. Ажажа, А.С. Бакай, И.B. Гурин, А.Н. Довбня, Н.В. Демидов, А.И. Зыков, Э.С. Злуницын, С.Д. Лавриненко,
Л.К. Мякушко, О.А. Репихов, А.В. Торговкин, Б.М. Широков, Б.И. Шраменко
На линейном ускорителе электронов ЛУ-10 НИК «Ускоритель» ННЦ ХФТИ создана установка “Стенд для радиаци
онных испытаний”, позволяющая проводить исследования коррозионной стойкости образцов различных модификаций
сплавов типа “хастеллой ”в расплаве фторидных солей циркония и натрия при высокой температуре.В радиационном
поле пучка электронов с энергией ∼10 МэВ и средним током ∼500 мкА (мощностью ∼5 кВт ) в течение 700 ч проведено
облучение сборки контейнеров с образцами. Сборка из 16 контейнеров (из углерод-углеродного композита), заполнен
ных исследуемыми образцами “хастелоя”в расплаве солей ZrF4 и NaF, помещалась в герметичную защитную оболочку
из нержавеющей стали. Сборка при облучении находилась в атмосфере аргона. Температура ее контролировалась тремя
термопарами. На протяжении всего процесса облучения обеспечивался стационарный температурный режим
(650 ± 15)оС.
СТЕНД ДЛЯ РАДІАЦІЙНИХ ВИПРОБУВАНЬ
КОНСТРУКЦІЙНИХ МАТЕРІАЛІВ В УМОВАХ СОЛЬОВОГО РЕАКТОРА
В.М. Ажажа, О.С Бакай, И.B. Гурін, А.М. Довбня, М.В. Демидов,А.І. Зиков, Э.С. Злуніцин, С.Д. Лавриненко,
Л.К. Мякушко, O.О. Репіхов,О.В. Торговкін, Б.М. Широков, Б.І. Шраменко
На лінійному прискорювачі електронів ЛП−10 НДК «Прискорювач» ННЦ ХФТІ створено установку “Стенд для
радіаційних випробувань”, яка дозволяє проводити дослідження корозійної стійкості зразків різних модифікацій сплавів
типу “хастелой ”в разплаві фторидних солей цирконію та натрію при високій температурі. У радіаційному полі пучка
електронів з енергією ∼10 МеВ та среднім струмом ∼500 мкА (потужністю ∼5 кВт ) впродовж 700 годин проведено
опромінення збірки контейнерів з досліджуваними зразками. Збірку з 16 контейнерів (з вуглець-вугецевого композиту),
заповнених зразками “хастелою”в расплаві солей ZrF4 та NaF, розміщено в герметичній захистній оболонці з нержавію
_______________________________________________________________________________
ВОПРОСЫ АТОМНОЙ НАУКИ И ТЕХНИКИ. 2005. №.4.
Серия: Физика радиационных повреждений и радиационное материаловедение (87), с. 20-23.
23
чої сталі. Збірка при опроміненні знаходилась в атмосфері аргону. Температура збірки контролювалась трьома те
рмопарами.. Впродовж процесу опромінення підтримувався стаціонарний температурний режим: (650 ± 15оС).
_______________________________________________________________________________
ВОПРОСЫ АТОМНОЙ НАУКИ И ТЕХНИКИ. 2005. №.4.
Серия: Физика радиационных повреждений и радиационное материаловедение (87), с. 20-23.
24
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| id | nasplib_isofts_kiev_ua-123456789-80538 |
| institution | Digital Library of Periodicals of National Academy of Sciences of Ukraine |
| issn | 1562-6016 |
| language | English |
| last_indexed | 2025-12-07T16:38:26Z |
| publishDate | 2005 |
| publisher | Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
| record_format | dspace |
| spelling | Azhazha, V.M. Bakai, A.S. Gurin, I.V. Dovbnya, A.M. Demidov, M.V. Zykov, A.I. Zlunitsyn, E.S. Lavrynenko, S.D. Myakushko, L.K. Repikhov, O.A. Torgovkin, O.V. Shirokov, B.M. Shramenko, B.I. 2015-04-18T18:47:34Z 2015-04-18T18:47:34Z 2005 Electron irradiation test facility for irradiation of structural materials in conditions of molten salt reactor / V.M. Azhazha, A.S. Bakai, I.V. Gurin, A.M. Dovbnya, M.V. Demidov, A.I. Zykov, E.S. Zlunitsyn, S.D. Lavrynenko, L.K. Myakushko, O.A. Repikhov, O.V. Torgovkin,B.M. Shirokov, B.I. Shramenko // Вопросы атомной науки и техники. — 2005. — № 4. — С. 20-23. — Бібліогр.: 1 назв. — англ. 1562-6016 PACS:41.60. https://nasplib.isofts.kiev.ua/handle/123456789/80538 A new device, Electron Irradiation Test Facility (EITF), has been created at electron linear accelerator Linac-10 at Accelerator R&D Complex affiliated with NSC KIPT. This facility allows to carry on studies on corrosion resistance of differently shaped samples of the Hastelloy type alloys in the melt of zirconium and sodium fluoride salts at high temperature. A container assembly (CA) that held samples was irradiated for 700 hours in the radiation field of electron beam with the energy ∼10 MeV and average current ∼500 microAmps (power∼5 kW ). The CA consisting of 16 containers (made of a carbon-carbon composite) that were loaded with research samples of Hastelloy alloys in the melt of the salts ZrF₄ и NaF was placed in air-tight protective shell made of stainless steel. During the irradiation, the CA was placed in argon atmosphere. The CA temperature was monitored with three thermocouples. Over the entire length of the irradiation process the stationary temperature regime was provided: 650°С ± 15°С. На лінійному прискорювачі електронів ЛП−10 НДК «Прискорювач» ННЦ ХФТІ створено установку “Стенд для радіаційних випробувань”, яка дозволяє проводити дослідження корозійної стійкості зразків різних модифікацій сплавів типу “хастелой ”в разплаві фторидних солей цирконію та натрію при високій температурі. У радіаційному полі пучка електронів з енергією ∼10 МеВ та среднім струмом ∼500 мкА (потужністю ∼5 кВт ) впродовж 700 годин проведено опромінення збірки контейнерів з досліджуваними зразками. Збірку з 16 контейнерів (з вуглець-вугецевого композиту), заповнених зразками “хастелою”в расплаві солей ZrF₄ та NaF, розміщено в герметичній захистній оболонці з нержавіючої сталі. Збірка при опроміненні знаходилась в атмосфері аргону. Температура збірки контролювалась трьома термопарами.. Впродовж процесу опромінення підтримувався стаціонарний температурний режим: (650 ± 15°С). На линейном ускорителе электронов ЛУ-10 НИК «Ускоритель» ННЦ ХФТИ создана установка “Стенд для радиационных испытаний”, позволяющая проводить исследования коррозионной стойкости образцов различных модификаций сплавов типа “хастеллой ”в расплаве фторидных солей циркония и натрия при высокой температуре.В радиационном поле пучка электронов с энергией ∼10 МэВ и средним током ∼500 мкА (мощностью ∼5 кВт ) в течение 700 ч проведено облучение сборки контейнеров с образцами. Сборка из 16 контейнеров (из углерод-углеродного композита), заполненных исследуемыми образцами “хастелоя”в расплаве солей ZrF₄ и NaF, помещалась в герметичную защитную оболочку из нержавеющей стали. Сборка при облучении находилась в атмосфере аргона. Температура ее контролировалась тремя термопарами. На протяжении всего процесса облучения обеспечивался стационарный температурный режим (650 ± 15)°С. The research was supported in part by STCU, Project # 294. en Національний науковий центр «Харківський фізико-технічний інститут» НАН України Вопросы атомной науки и техники Electron irradiation test facility for irradiation of structural materials in conditions of molten salt reactor Стенд для радіаційних випробувань конструкційних матеріалів в умовах сольового реактора Стенд для радиационных испытаний конструкционных материалов в условиях солевого реактора Article published earlier |
| spellingShingle | Electron irradiation test facility for irradiation of structural materials in conditions of molten salt reactor Azhazha, V.M. Bakai, A.S. Gurin, I.V. Dovbnya, A.M. Demidov, M.V. Zykov, A.I. Zlunitsyn, E.S. Lavrynenko, S.D. Myakushko, L.K. Repikhov, O.A. Torgovkin, O.V. Shirokov, B.M. Shramenko, B.I. |
| title | Electron irradiation test facility for irradiation of structural materials in conditions of molten salt reactor |
| title_alt | Стенд для радіаційних випробувань конструкційних матеріалів в умовах сольового реактора Стенд для радиационных испытаний конструкционных материалов в условиях солевого реактора |
| title_full | Electron irradiation test facility for irradiation of structural materials in conditions of molten salt reactor |
| title_fullStr | Electron irradiation test facility for irradiation of structural materials in conditions of molten salt reactor |
| title_full_unstemmed | Electron irradiation test facility for irradiation of structural materials in conditions of molten salt reactor |
| title_short | Electron irradiation test facility for irradiation of structural materials in conditions of molten salt reactor |
| title_sort | electron irradiation test facility for irradiation of structural materials in conditions of molten salt reactor |
| url | https://nasplib.isofts.kiev.ua/handle/123456789/80538 |
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