Investigation of erosion mechanisms and erosion products in divertor armour materials under conditions relevant to ELMs and mitigated disruptions in ITER
Carbon fibre composite (CFC) and tungsten were irradiated by intense plasma streams at plasma gun facilities MK-200UG and QSPA-T. The targets were tested by plasma loads relevant to Edge Localised Modes (ELM) and mitigated disruptions in ITER. Onset condition of material erosion and properties of er...
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Національний науковий центр «Харківський фізико-технічний інститут» НАН України
2008
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| Cite this: | Investigation of erosion mechanisms and erosion products in divertor armour materials under conditions relevant to ELMs and mitigated disruptions in ITER / V.M. Safronov, N.I. Arkhipov, N.S. Klimov, D.V. Kovalenko, I.S. Landman, A.A. Moskacheva, S.E. Pestchanyi V.L. Podkovyrov, I.M. Poznyak, D.A. Toporkov, A.M. Zhitlukhin // Вопросы атомной науки и техники. — 2008. — № 6. — С. 52-54. — Бібліогр.: 11 назв. — англ. |
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Digital Library of Periodicals of National Academy of Sciences of Ukraine| _version_ | 1859673228906070016 |
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| author | Safronov, V.M. Arkhipov, N.I. Klimov, N.S. Kovalenko, D.V. Landman, I.S. Moskacheva, A.A. Pestchanyi, S.E. Podkovyrov, V.L. Poznyak, I.M. Toporkov, D.A. Zhitlukhin, A.M. |
| author_facet | Safronov, V.M. Arkhipov, N.I. Klimov, N.S. Kovalenko, D.V. Landman, I.S. Moskacheva, A.A. Pestchanyi, S.E. Podkovyrov, V.L. Poznyak, I.M. Toporkov, D.A. Zhitlukhin, A.M. |
| citation_txt | Investigation of erosion mechanisms and erosion products in divertor armour materials under conditions relevant to ELMs and mitigated disruptions in ITER / V.M. Safronov, N.I. Arkhipov, N.S. Klimov, D.V. Kovalenko, I.S. Landman, A.A. Moskacheva, S.E. Pestchanyi V.L. Podkovyrov, I.M. Poznyak, D.A. Toporkov, A.M. Zhitlukhin // Вопросы атомной науки и техники. — 2008. — № 6. — С. 52-54. — Бібліогр.: 11 назв. — англ. |
| collection | DSpace DC |
| container_title | Вопросы атомной науки и техники |
| description | Carbon fibre composite (CFC) and tungsten were irradiated by intense plasma streams at plasma gun facilities MK-200UG and QSPA-T. The targets were tested by plasma loads relevant to Edge Localised Modes (ELM) and mitigated disruptions in ITER. Onset condition of material erosion and properties of erosion products have been studied.
С-С композит і вольфрам були піддані впливові інтенсивних потоків плазми на плазмових прискорювачах МК-200UG і КСПП-Т. Мішені випробувалися при плазмових навантаженнях, характерних для ЭЛМів й ослаблених зривів в ІТЕРі. Були проведені дослідження початкових умов ерозії матеріалів і властивостей продуктів ерозії.
С-С композит и вольфрам были подвергнуты воздействию интенсивных потоков плазмы на плазменных ускорителях МК-200UG и КСПУ-Т. Мишени испытывались при плазменных нагрузках, характерных для ЭЛМов и ослабленных срывов в ИТЭРе. Были проведены исследования начальных условий эрозии материалов и свойств продуктов эрозии.
|
| first_indexed | 2025-11-30T14:39:33Z |
| format | Article |
| fulltext |
ITER AND FUSION REACTOR ASPECTS
INVESTIGATION OF EROSION MECHANISMS AND EROSION
PRODUCTS IN DIVERTOR ARMOUR MATERIALS UNDER CONDITIONS
RELEVANT TO ELMS AND MITIGATED DISRUPTIONS IN ITER
V.M. Safronov1, N.I. Arkhipov1, N.S. Klimov1, D.V. Kovalenko1, I.S. Landman2, A.A. Moskacheva1,
S.E. Pestchanyi2, V.L. Podkovyrov1, I.M. Poznyak3, D.A. Toporkov1, A.M. Zhitlukhin1
1 State Research Center of Russian Federation Troitsk Institute for Innovation and Fusion
Research, Troitsk, Moscow reg., Russia, e-mai: vsafr@triniti.ru;
2Forschungszentrum Karlsruhe, IHM, Karlsruhe, Germany;
3 Moscow Institute of Physics and Technology, Dolgoprudnyi, Moscow reg., Russia
Carbon fibre composite (CFC) and tungsten were irradiated by intense plasma streams at plasma gun facilities MK-
200UG and QSPA-T. The targets were tested by plasma loads relevant to Edge Localised Modes (ELM) and mitigated
disruptions in ITER. Onset condition of material erosion and properties of erosion products have been studied.
PACS: 52.75.–d, 52.70.–m, 52.40.Hf, 28.52
1. INTRODUCTION
Carbon-fibre composite (CFC) and tungsten are
foreseen presently as armour materials for the divertor
targets in ITER. During the transient processes, such as
ELMs and mitigated disruptions, the targets are exposed
to the plasma heat loads up to 10 MJ/m2 on the time scale
of order of 1 ms that can cause a severe erosion of the
armour materials [1]. Plasma-induced erosion is a major
concern for safe, successful and reliable reactor operation.
Erosion restricts lifetime of the divertor components,
leads to contamination of hot plasma by heavy impurities
and can produce a substantial amount of the material dust,
which being tritiated, radioactive and chemically reactive
presents a serious problem for a safety. The exact amount
and properties of the eroded materials are critically
important to analysis of tokamak-reactor.
The ITER transient loads are not achieved in the
existing tokamak machines. Therefore, erosion of
candidate armour materials is investigated by use of
powerful plasma guns [2-4] and e-beam facilities [5,6],
which are capable to simulate, at least in part, the loading
condition of interest. In the present work, the CFC and
tungsten targets have been tested by intense plasma
streams at the pulsed plasma gun MK-200UG and quasi-
stationary plasma gun QSPA-T. The targets were
examined by plasma heat fluxes relevant to ITER ELMs
and mitigated disruptions. Primary attention has been
focused at investigation of erosion onset conditions and
properties of erosion products.
2. EXPERIMENTAL TECHNIQUE
2.1. MK-200UG EXPERIMENT
At MK-200UG facility, the targets are tested by
magnetized hydrogen plasma streams with heat load
q = 0.05…1 MJ/m2 and pulse duration τ=0.05 ms. The
plasma heat load q varies by changing the plasma density in
the range n = (0.1…2)×1020 m-3 while the impact ion energy
remains practically unaltered Ei = 2…3 keV. Plasma
pressure varies in the range P = 0.03…0.5 bar. Diameter of
the plasma stream d = 0.06…0.1 m. Plasma/target
interaction occurs in the magnetic field B = 0.5…2 T.
Plasma stream parameters such as heat flux w = q/τ, impact
ion energy Ei, density n, pressure P, and negligible percentage
of impurities (<1%) are close to the expected in ITER during
transient processes. The disadvantage of MK-200UG facility is
small duration τ of the plasma pulse and it is not suited for
longevity test of the divertor materials. Nevertheless the facility
is quite suitable to simulate the initial stage of the ITER transient
events and to study the plasma/material interaction under rather
realistic plasma parameters.
The present experiment at MK-200UG was aimed at
- measurement of melting and boiling points for
tungsten i.e. quantification of minimum heat
load causing tungsten surface melting and
boiling;
- determination of evaporation point for CFC and
investigation of carbon vapor properties.
These experimental data need for development and
validation of appropriate numerical models [7-9].
Calorimeters, photo cameras, infrared pyrometer, and
spectrometers have been used as diagnostics.
2.2. QSPA-T EXPERIMENT
At QSPA-T facility, the targets are irradiated by
hydrogen plasma steams with the pulse duration 0.5 ms
and heat load 0.1…2.5 MJ/m2. The plasma load condition
is relevant to the ITER transients; therefore the facility is
applied for longevity testing of candidate armour
materials and investigation of the erosion mechanisms,
erosion products, and the resultant surface damage.
Taking into account that the facility is not equipped by the
magnetic field and the plasma stream density n ≥ 1022 m-3
and pressure P = 1…7 bar is larger than in tokamak
plasma, the QSPA-T experiment seems to give the upper
limit of erosion, which might be expected in ITER.
Onset conditions of CFC and tungsten erosion have been
studied in the present QSPA-T experiment. The erosion was
quantified by means of mass loss measurements and analysis
of the exposed surface damage with profilometer and
microscope. Droplets and particles emitted from the target
surface due to macroscopic erosion mechanisms have been
studied by use of diagnostics based on CCD camera.
3. EXPERIMENTAL RESULTS
3.1. EROSION OF CFC TARGET
Under action of intense plasma stream the CFC target
is eroded mainly due to the thermal evaporation and
brittle destruction [8]. Both of these erosion mechanisms
52 PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. 2008. № 6.
Series: Plasma Physics (14), p. 52-54.
are realized when the surface heats up to the temperature
T ≈ 4000 K. Evaporation of the target surface and
evaporation of small carbon particles, which are formed
due to CFC brittle destruction, results in formation of
carbon vapor in front of the target surface.
Onset condition of CFC evaporation has been
experimentally studied at MK-200UG. The target was
irradiated by increasing heat load and visible
spectroscopy was applied for detection of carbon vapor
appearance. Infrared pyrometer was used for online
measurement of the target surface temperature Ts(t). It’s
found that the evaporation is absent at the plasma load
q ≤ 0.1 MJ/m2 (Ts ≤ 2200 K); weak evaporation takes
place at q ≈ 0.15 MJ/m2 (Ts ≈ 3000 K); intense
evaporation starts at q = 0.2 MJ/m2 (Ts ≈ 4000 K). The
surface temperature grows with the plasma load, it runs
up to a peak value of Ts ≈ 4000 K at q = 0.2 MJ/m2 and
remains unaltered with further increase of the plasma
load. The plasma load q = 0.2 MJ/m2, which heats the
surface to the sublimation point, corresponds to a
threshold of intense CFC evaporation.
0
0.5
1
1.5
2
2.5
0.15 0.2 0.25 0.3 0.35 0.4
El
ec
tr
on
d
en
si
ty
, 1
023
m
-3
Plasma load, MJ/m2
Fig.1. Electron density of carbon vapor plasma
(MK-200UG, 0.5-cm distance from target surface)
The evaporated carbon is ionized quickly and carbon
plasma arises. Spectrum of carbon plasma consists of
spectral lines of C+1–C+5 ions, continuous spectrum is
observed near the surface at distances ≤ 1 mm. Electron
density ne of carbon plasma evaluated from Stark
broadening of spectral line CIV(4658.3Ao) is shown in
Fig.1. At low heat loads the density rises steeply:
variation of q from 0.17 to 0.20 MJ/m2 results in increase
of ne by a factor of 10. At q > 0.20 MJ/m2 the density
grows slightly keeping at a level of ne=2×1023 m-3. This
experimental fact confirms also that a threshold of intense
CFC evaporation is about q = 0.2 MJ/m2.
At q = 0.1…0.15 MJ/m2 the density of carbon plasma
was too small to be measured by the applied diagnostics.
But after the target was exposed to 200 plasma shots the
density increases to the measurable magnitude ne=(3…4)×
1021 m-3 at the same plasma load. Properties of CFC seem
to be degraded during multiple plasma exposures that lead
to intensification of vaporization.
Numerical simulation for CFC surface temperature
evolution under the plasma exposure has been done using
PEGASUS-3D code [8]. Temperature dependence for
CFC thermal conductivity at T=2500…4000 K was taken
from analytical extrapolation of the thermoconductivity
measured at T ≤ 2500K [10]. The performed simulation
reveals that the reference thermal conductivity λref is
incompatible with the measured temperature. According
to numerical modeling an intense evaporation with λref
should start at q=0.3 MJ/m2 while in the experiment it
happens at q=0.2 MJ/m2. It was assumed that a real
thermal conductivity differs from the reference one
because of degradation of CFC properties due to plasma
irradiation. Most probable reason for this degradation is
brittle CFC destruction caused by multiple thermal shocks
[8]. The best fit for the experimental results corresponds
to the reduction of λref by a factor about 3.
Similar results have been obtained at QSPA-T facility
[11]. The obtained experimental data (Fig.2) demonstrate
clearly that the CFC erosion starts at essentially lower
plasma loads than it follows from calculation data
obtained for the reference thermal conductivity λref .
Fig.2. CFC erosion at QSPA-T
The performed experimental studies have shown that
the CFC resistance against action of intense plasma
streams is worth than it was expected before. It should be
noted also that carbon plasma formed due to CFC erosion
expands from the target along the magnetic field lines
with a velocity V=(1…2)×104 m/s. Density of carbon ions
measured at MK-200UG facility at 15-cm distance is nc ≥
1021m-3 that is larger than a density of tokamak plasma. It
means that during ELMs large amount of carbon
impurities might move from the divertor to the main
chamber causing a contamination of hot plasma.
3.1. EROSION OF TUNGSTEN TARGET
At MK-200UG and QSPA-T facilities there were
measured the minimal plasma loads qm and qb, which
cause tungsten surface heating to melting and boiling
temperatures (Tm = 3650 K, Tb ≈ 6000 K):
MK-200UG - qm = 0.30 MJ/m2; qb = 0.65 MJ/m2;
QSPA-T - qm = 1 MJ/m2; qb = 2.2 MJ/m2.
At the time-constant heat flux the integral plasma load
q, which is required for surface heating to a certain
temperature Ts, is proportional to τ1/2. Taking into account
that the plasma pulse duration at QSPA-T (τ = 0.5 ms) is
10 times larger than at MK-200UG (τ = 0.05 ms) the data
obtained at both facilities are in a good agreement. The
experimental data agree also with the result of numerical
modeling.
53
Fig3. Mass loss of tungsten
Onset condition of tungsten erosion has been studied
at QSPA-T facility. The tungsten target was tested at
varying plasma load and a mass loss was measured. At
the plasma load below the melting point q < 1 MJ/m2 the
mass loss is negligible but it rises steeply at q> qm (Fig.3).
Fig.4. Emission of droplets from tungsten target
The mass loss results from melt layer splashing and
emission of droplets under the stream action (Fig.4).
SUMMARY
CFC and tungsten targets were tested by intense
plasma streams at heat fluxes relevant to ELMs and
mitigated disruptions in ITER.
Intense evaporation of CFC happens at lower plasma
load than it results from the numerical modeling based on
the reference thermal conductivity. Degradation of the
thermal conductivity could be caused by brittle CFC
destruction under multiple plasma exposures.
Erosion of tungsten begins with the surface melting.
The erosion is caused mainly by melt splashing.
Erosion of tungsten target starts at larger plasma load
than CFC erosion.
ACKNOWLEDGEMENTS
The work is supported partly by RFBR grant No 08-
02-13612.
REFERENCES
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v. 41, p.1523.
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3.V.I. Tereshin et al.// J. Nucl. Mater. 2003, v. 313-316,
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4.V. Belan et al.// J. Nucl. Mater. 1996, v. 233-237,
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5.V.T. Astrelin et al.// Nucl. Fusion. 1997, v. 37, p.1541.
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7.I.S. Landman et al.// J. Nucl. Mater. 2005, v. 337-339,
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10.ITER MATERIAL PROPERTIES HANDBOOK.
11.A. Zhitlukhin et al.// J. Nucl. Mater. 2007, v. 363-365,
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Article received 25.09.08.
ИССЛЕДОВАНИЕ МЕХАНИЗМОВ И ПРОДУКТОВ ЭРОЗИИ ОБЛИЦОВОЧНЫХ МАТЕРИАЛОВ
ДИВЕРТОРА В УСЛОВИЯХ, ХАРАКТЕРНЫХ ДЛЯ ЭЛМов И ОСЛАБЛЕННЫХ СРЫВОВ В ИТЭРе
В.M. Сафронов, Н.И. Архипов, Н.С. Климов, Д.В. Коваленко, И.С. Ландман,
А.А. Москачева,С.Е. Песчаный, В.Л. Подковыров, И.М. Позняк, Д.А. Топорков, А.М. Житлухин
С-С композит и вольфрам были подвергнуты воздействию интенсивных потоков плазмы на плазменных
ускорителях МК-200UG и КСПУ-Т. Мишени испытывались при плазменных нагрузках, характерных для
ЭЛМов и ослабленных срывов в ИТЭРе. Были проведены исследования начальных условий эрозии материалов
и свойств продуктов эрозии.
ДОСЛІДЖЕННЯ МЕХАНІЗМІВ І ПРОДУКТІВ ЕРОЗІЇ ОБЛИЦЮВАЛЬНИХ МАТЕРІАЛІВ
ДИВЕРТОРА В УМОВАХ, ХАРАКТЕРНИХ ДЛЯ ЭЛМів І ОСЛАБЛЕНИХ ЗРИВІВ В ІТЕРі
В.M. Сафронов, М.І. Архипов, М.С. Клімов, Д.В. Коваленко, І.С. Ландман,
А.А. Москачова, С.Є. Песчаний, В.Л. Подковиров, І.М. Позняк, Д.А. Топорков, О.М. Житлухін
С-С композит і вольфрам були піддані впливові інтенсивних потоків плазми на плазмових прискорювачах
МК-200UG і КСПП-Т. Мішені випробувалися при плазмових навантаженнях, характерних для ЭЛМів й
ослаблених зривів в ІТЕРі. Були проведені дослідження початкових умов ерозії матеріалів і властивостей
продуктів ерозії.
54
INVESTIGATION OF EROSION MECHANISMS AND EROSION PRODUCTS IN DIVERTOR ARMOUR MATERIALS UNDER CONDITIONS RELEVANT TO ELMS AND MITIGATED DISRUPTIONS IN ITER
REFERENCES
|
| id | nasplib_isofts_kiev_ua-123456789-110799 |
| institution | Digital Library of Periodicals of National Academy of Sciences of Ukraine |
| issn | 1562-6016 |
| language | English |
| last_indexed | 2025-11-30T14:39:33Z |
| publishDate | 2008 |
| publisher | Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
| record_format | dspace |
| spelling | Safronov, V.M. Arkhipov, N.I. Klimov, N.S. Kovalenko, D.V. Landman, I.S. Moskacheva, A.A. Pestchanyi, S.E. Podkovyrov, V.L. Poznyak, I.M. Toporkov, D.A. Zhitlukhin, A.M. 2017-01-06T13:04:52Z 2017-01-06T13:04:52Z 2008 Investigation of erosion mechanisms and erosion products in divertor armour materials under conditions relevant to ELMs and mitigated disruptions in ITER / V.M. Safronov, N.I. Arkhipov, N.S. Klimov, D.V. Kovalenko, I.S. Landman, A.A. Moskacheva, S.E. Pestchanyi V.L. Podkovyrov, I.M. Poznyak, D.A. Toporkov, A.M. Zhitlukhin // Вопросы атомной науки и техники. — 2008. — № 6. — С. 52-54. — Бібліогр.: 11 назв. — англ. 1562-6016 PACS: 52.75.–d, 52.70.–m, 52.40.Hf, 28.52 https://nasplib.isofts.kiev.ua/handle/123456789/110799 Carbon fibre composite (CFC) and tungsten were irradiated by intense plasma streams at plasma gun facilities MK-200UG and QSPA-T. The targets were tested by plasma loads relevant to Edge Localised Modes (ELM) and mitigated disruptions in ITER. Onset condition of material erosion and properties of erosion products have been studied. С-С композит і вольфрам були піддані впливові інтенсивних потоків плазми на плазмових прискорювачах МК-200UG і КСПП-Т. Мішені випробувалися при плазмових навантаженнях, характерних для ЭЛМів й ослаблених зривів в ІТЕРі. Були проведені дослідження початкових умов ерозії матеріалів і властивостей продуктів ерозії. С-С композит и вольфрам были подвергнуты воздействию интенсивных потоков плазмы на плазменных ускорителях МК-200UG и КСПУ-Т. Мишени испытывались при плазменных нагрузках, характерных для ЭЛМов и ослабленных срывов в ИТЭРе. Были проведены исследования начальных условий эрозии материалов и свойств продуктов эрозии. The work is supported partly by RFBR grant No 08- 02-13612. en Національний науковий центр «Харківський фізико-технічний інститут» НАН України Вопросы атомной науки и техники ITER and fusion reactor aspects Investigation of erosion mechanisms and erosion products in divertor armour materials under conditions relevant to ELMs and mitigated disruptions in ITER Дослідження механізмів і продуктів ерозії облицювальних матеріалів дивертора в умовах, характерних для ЭЛМів і ослаблених зривів в ІТЕРі Исследование механизмов и продуктов эрозии облицовочных материалов дивертора в условиях, характерных для ЭЛМов и ослабленных срывов в ИТЭРе Article published earlier |
| spellingShingle | Investigation of erosion mechanisms and erosion products in divertor armour materials under conditions relevant to ELMs and mitigated disruptions in ITER Safronov, V.M. Arkhipov, N.I. Klimov, N.S. Kovalenko, D.V. Landman, I.S. Moskacheva, A.A. Pestchanyi, S.E. Podkovyrov, V.L. Poznyak, I.M. Toporkov, D.A. Zhitlukhin, A.M. ITER and fusion reactor aspects |
| title | Investigation of erosion mechanisms and erosion products in divertor armour materials under conditions relevant to ELMs and mitigated disruptions in ITER |
| title_alt | Дослідження механізмів і продуктів ерозії облицювальних матеріалів дивертора в умовах, характерних для ЭЛМів і ослаблених зривів в ІТЕРі Исследование механизмов и продуктов эрозии облицовочных материалов дивертора в условиях, характерных для ЭЛМов и ослабленных срывов в ИТЭРе |
| title_full | Investigation of erosion mechanisms and erosion products in divertor armour materials under conditions relevant to ELMs and mitigated disruptions in ITER |
| title_fullStr | Investigation of erosion mechanisms and erosion products in divertor armour materials under conditions relevant to ELMs and mitigated disruptions in ITER |
| title_full_unstemmed | Investigation of erosion mechanisms and erosion products in divertor armour materials under conditions relevant to ELMs and mitigated disruptions in ITER |
| title_short | Investigation of erosion mechanisms and erosion products in divertor armour materials under conditions relevant to ELMs and mitigated disruptions in ITER |
| title_sort | investigation of erosion mechanisms and erosion products in divertor armour materials under conditions relevant to elms and mitigated disruptions in iter |
| topic | ITER and fusion reactor aspects |
| topic_facet | ITER and fusion reactor aspects |
| url | https://nasplib.isofts.kiev.ua/handle/123456789/110799 |
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