10th itpa conference, avila, 7-10 jan. 2008 changes of deuterium retention properties on metals due...
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10th ITPA conference, Avila, 7-10 Jan. 2008
Changes of Deuterium Retention Properties on Metals due to the Helium Irradiation or Impurity
Deposition
M.Tokitani 2), H. Iwakiri 1), N. Yoshida 1),S. Masuzaki 2), N. Ashikawa 2)
1) Kyushu University2) National Insititute for Fusion Science
Y
L
oshida
aboratoryY
L
oshida
aboratory
Research Institute for Applied Mechanics
10th ITPA conference, Avila, 7-10 Jan. 2008
Bombarding plasma facing components with helium causes changing of their
properties• He ash: divertor• He GDC: divertor & first wall• CX neutral: divertor & first wall
surface
mV-nHe
He Long range diffusion of He
He+
He V
I
Stable structure
Resistance
Instable
Long range diffusion of interstitial atoms
Aggregation of I
I‐loop formation
He ion, atom
Annihilation?
10th ITPA conference, Avila, 7-10 Jan. 2008
Effects of pre-irradiation of
heliumIncrease of helium bubble and dislocation loops densities causes increase of strongly trapped deuterium retention.
In a fixed helium bubble and dislocation loops densities case, deuterium trapping sites are changed depending on D fluence.
Lower fluence : strongly trappedHigher fluence : strong trap sites are
filled, and weakly trapped D increase.
300 400 500 600 700 800 9000.0
0.5
1.0
1.5
2.0
2.5
3.0
3.5
4.0x1018
1x1022D2+/m2
4x1021
1x1021
5x1020
No He 1x1022
Temperature (K)
Des
orp
tio
n R
ate
(D2/m
2s)
300 400 500 600 700 800 9000
2x1017
4x1017
6x1017
8x1017
1x1018
8x10 21He+/m 2
2x10 21He +/m 2
1x10 20He+/m 2
no He irr.
Des
orp
tio
n R
ate
(D2/m
2 s)
W8keV,1 x 1021D2
+/m2 @300K
8keV, 2 x 1021He+/m2 @ 300K
10th ITPA conference, Avila, 7-10 Jan. 2008
Bri
gh
t fi
eld
im
ages
Ne-GDH-GDHe-GDUn-irradiation
Dar
k fi
eld
im
ages
20nm
20nm
Specimens surfaces analysis Specimens surfaces analysis after exposed to three glow discharges (TEM)after exposed to three glow discharges (TEM)
Incident energy of ions are 200-300eV, and temperature of specimens were almost room temperature.
In contrast with the very heavy damages observed in the case of He-GD, these defects were not observed in the case of H-GD and Ne-GD.
10th ITPA conference, Avila, 7-10 Jan. 2008
Depth distribution of He bubblesDepth distribution of He bubblesH
e co
nce
ntr
atio
n [
a.u
.]
a) LHD He-GDC
(200eV , 65h)
20 30 4010 500Depth [nm]
b) He+ irra. exp. (2keV-He+,1.0x1022)
TRIM-91TRIM-91(2keV-He(2keV-He++))
TRIM-91TRIM-91(200eV-He(200eV-He++))
Cross-sectional TEM observation by using FIB technique after He-GDC
Stereoscopic observation by TEM
10nm
HeHe(1)
(2)
(1) Deposition layer with about 10nm thick, very heavy damage such as large bubbles formation and surface roughening.
(2) In bulk, about 30nm thick, small helium bubbles (1-2nm) were formed in the matrix.
By using He-GDC, serious irradiation defects are formed in the deep range.By using He-GDC, serious irradiation defects are formed in the deep range.
Stainless steel specimen (SUS316L)
10th ITPA conference, Avila, 7-10 Jan. 2008
Un-exposed surfaceUn-exposed surface
Exposed surfaceExposed surface
m
m
[nm]653
00
10 0
10
550
The feature of Ne-GDCThe feature of Ne-GDC
(b) Ne-GDC
10nm
NeNe
Surface erosion of SUS316L after Ne-GDC as observed by AFM
Cross-sectional TEM observation by using FIB technique after Ne-GDC
Ne-GDC can remove the surface efficiently by a high sputtering yield.
A smooth surface and a no-defects internal structure can be obtained by using Ne-GDC.
10th ITPA conference, Avila, 7-10 Jan. 2008
He-GDC(65h) H-GDC(71.5h) Ne-GDC(55h)
Retention of Deuterium after GDCsRetention of Deuterium after GDCsAdditional deuterium irradiation to the specimen pre-exposed to three GDC were conducted in order to confirm the change of deuterium retention properties due to the GDCs.
300 350 400 450 500 5500.0
5.0x1017
1.0x1018
1.5x1018
2.0x1018 After He-GDC After H-GDC After Ne-GDC
D2 d
eso
rpti
on
rat
e [D
2/m2 s]
Temperature [K]
Fresh specimenFresh specimen(irradiated only D(irradiated only D++))
Total retention of deuterium becomes lower by performing GDCs.
►Reduction of oxidized film.
He-GDC showed highest deuterium retention among the three GDCs.
Ne-GDC showed lowest deuterium retention.
In H-GDC, most of the retained deuterium desorbs up to 370K.
SUS316L
2keV-D+
1.0x1022[D+/m2]
Room temp.
10th ITPA conference, Avila, 7-10 Jan. 2008
Y. Ueda reported in ICFRM 2007 that:Only 0.1% of He strongly affects H inward diffusion in W. Stress field around bubbles and reduction of effective diffusion area (diffusion through bubbles is unlikely) could reduce H diffusion.
In Ueda’s experiment, incident energy of deuterium and helium is 0.33keV and 1keV, respectively.In LHD glow discharge case, incident energy of deuterium and helium are 2keV and 200eV (glow discharge), respectively.
The difference of ranges of hydrogen isotopes and helium could be a key parameter.
Blistering suppression by simultaneous H and He ion beam irradiation
Mechanism of retention modification by He irradiation
10th ITPA conference, Avila, 7-10 Jan. 2008
Possible mechanism for the change of hydrogen isotope
retention propertiesStress field caused by bubbles and displacements and/or reduction of diffusion area could reduce hydrogen isotope transport in bulk.
Damaged regionRange of hydrogen isotopes
diffusion
diffusion
Deposition layer on the surface also a possible mechanism for reduction of hydrogen isotope release from the surface
10th ITPA conference, Avila, 7-10 Jan. 2008
Summary• Hydrogen isotope retention properties in metal are changed by helium irradiatio
n.
– Increase of hydrogen isotope retention is observed after helium ion beam (8 keV) irradiation.
– The influence of the GDCs on the deuterium retention was also examined. The sample exposed to He-GDC showed highest deuterium retention while Ne-GDC showed lowest.
• Stress field caused by bubbles and displacements and/or reduction of diffusion area due to helium irradiation could be a barrier for hydrogen isotope transport.
– Difference of ranges of hydrogen isotope and helium could be a key parameter.
• Estimation of incident He energy (ash, CX) is necessary
– Systematic experiment is necessary to confirm this assumption.
• Material, temperature, and so on
• After neon glow discharge, there is almost no damage in sample, and hydrogen retention substantially decreases.
– Neon glow discharge can be a tool for wall conditioning in ITER