eu-pwi tf meeting, warsaw, 4-6 november 2009 fuel removal sewg report 2009 j. p. coad on behalf of...

EU-PWI TF meeting, Warsaw, 4-6 November 2009 EU Plasma-Wall Interactions Task Force

Fuel Removal SEWG report Fuel Removal SEWG report 20092009

J. P. Coad

On behalf of all those involved in Tasks for the SEWG

• Introduction• Chemical cleaning/inhibition using Oxygen and Nitrogen• Tokamak cleaning and conditioning techniques • Cleaning gaps and castellations• Laser removal and in-situ application• Conclusions

2/28

EU Plasma-Wall Interactions Task Force

Chemical cleaning/inhibition Chemical cleaning/inhibition using Oxygen and Nitrogenusing Oxygen and Nitrogen

3/28


0

0,2

0,4

0,6

0,8

1

0 5 10 15 20

N2 in plasma

N2 in sample

H

PN2(10

-6)

No

rmalized

C

Dep

osit

ion

0

0,2

0,4

0,6

0,8

1

0 0,5 1 1,5 2 2,5 3 3,5 4

NH3 in Plasma

NH3 in sample

No

rma

lize

d C

de

po

sit

ion

p NH3

(10-6

)

Scavenging effect of ammonia and nitrogen injected at two positions: in the plasmas (blue) and in in front of the deposition sample (red). Note the higher values of mass 28

required for the same inhibition effect

CONCLUSIONS- Better inhibition of carbon deposits by ammonia injection due to volatile HCN formation- NO difference between in-plasma/afterglow injection for ammonia

PILOT PSI Experiments

F Tabares, CIEMAT, in conjunction with FOM and MHEST

4/28


0

2 10-7

4 10-7

6 10-7

8 10-7

1 10-6

1,2 10-6

0 5 10-12 1 10-11 1,5 10-11 2 10-11

HCN

y = 1,2942e-07 + 53624x R= 0,96838

HC

N

NH3xDelta CH4

0

2 10-7

4 10-7

6 10-7

8 10-7

1 10-6

1,2 10-6

0 5 10-12 1 10-11 1,5 10-11 2 10-11 2,5 10-11 3 10-11 3,5 10-11 4 10-11

HCNy = 4,07e-07 + 18366x R= 0,67617

HC

N

CH4.delt NH3

0

2 10-7

4 10-7

6 10-7

8 10-7

1 10-6

1,2 10-6

0 2 10-12 4 10-12 6 10-12 8 10-12 1 10-11 1,2 10-11 1,4 10-11

HCN

y = 2,2739e-07 + 66546x R= 0,76518

HC

N

delt CH4.delt NH3

Radical/radical reaction Reaction 2: Delta NH3 ~ NH2 cc

Reaction 1: Delta CH4 ~ CH3 cc

Correlation of HCN formation from NH3/CH4 in RF ICP

M Mozetic, MHESTF Tabares, CIEMAT

Best correlation for HCN formation with Reaction 1


10CH4/8N2/2H2

• no scavenging effect has been detected• complete suppression of deposition on powered electrode is attributed to direct sputtering of the growing film by N2

+ ions •charge exchange reactions with molecules (methyl radicals) as well decrease the sticking probability

At high rf power, in high fragmentation condition of molecules, a complete suppression of the deposition has been observed above 300 W. The inhibition of deposition was attributed to the gas phase reaction between the film precursors, like CxHy, and atomic nitrogen. These results lead to conclusion that the scavenger effect produces volatile molecules such as hydrocarbons and hydrogen cyanide which are pumped away.

E Vassallo et al, ENEA-CRN

Inhibition of a-C:H films by N2 dilution in RF plasmas


MS of NH3 plasma at 8Pa

-

5.00

10.00

15.00

20.00

25.00

0 200 400 600 800 1000 1200

Nominal RF power [W]

Part

ial p

ress

ure

[x10

-7 m

bar]

M16

M17

M27

M28

Mass spectra of gas mixture passing through the discharge chamber(M 16, M 17 – NH3 M 27 – HCN M 28 – N2)

At low RF powers, the NH3 molecules are destroyed and N2 molecules are formed, causing a rise of partial pressure of N2.

At generator powers above 600 W the nitrogen in the discharge interacts with a-C:H films deposited on the walls of the vessel, resulting in a production of HCN.

Reaction of ammonia with a-C:H films in RF plasma

~

experimentalchamber

to pump

1200 Wradiofrequency

generator

separating tube 6mm

plasma

CH4 + H2NH3

NH3massspectrometer

Furnace, 200 C

NH3 is injected into a discharge created in a CH4 – H2 mixture.Prior to introduction of NH3, a-C:H film is formed on the walls of the discharge and experimental chamber.

M Mozetic, MHEST


~

6

7

4 3

1

2

5

1

2

3

4

5Experimental set-up:1 – discharge chamber, 2 – radiofrequency generator, 4 – narrow separating tube, 5 – experimental chamber, 6 – retractable catalytic probe, 7 – stationary probe. Shaded area represents the plasma.

Side-arm configuration:1 – probe housing, 2 – kovar finishing part, 3 – glass tube, 4 – probe tip, 5 – inserted aluminium foil covered by a-C:H

Measuring oxygen atom loss coeffs on a-C:H covered surfaces

MaterialRoughness

(nm)Hydrogen

content (%)Recombination

coefficient

a-C:H 40 40 (1.4 0.1) 10-3

a-C 10 5 (2.7 0.2) 10-3

Al foil 45 N/A (6.0 0.8) 10-4

Results

High reactivity => efficient a-C:H removalNo electric charge => unaffected by magnetic fields Good selectivity => minimal substrate damage

Neutral oxygen atoms:

M Mozetic, MHEST


P. Panjan, MHEST

Deposition of a-C(W/Mg):H films by triode sputtering

+

-

+

-

+

-

target

substrate holder

weak plasma

thermoionic arc

hot filamentinert gas, Ar

anode

reactive gas, C2H2, N2

heater

• Balzers sputtering system with thermionic arc

• Target: graphite, W / Mg

• Ar/C2H2 atmosphere

• Surface temperature below 120 C

0

20

40

60

80

100

0 50 100 150 200 250 300 350 400 450

Sputter Time (min)

Co

nce

ntr

atio

n (

at%

)

C

W

O

Cr

Fe

Schematic of film AES Profile


0

20

40

60

80

100

0 50 100 150 200 250 300 350 400 450

Sputter Time (min)

Co

nc

en

tra

tio

n (

at%

)

C

W

O

Cr

Fe

AES profile of untreated sample

0

20

40

60

80

100

0 50 100 150 200 250 300 350 400 450

Sputter Time (min)

Co

nce

ntr

atio

n (

at%

)WCOCrFe

C

W

O

Cr Fe

AES profile after 5 min of plasma

0

20

40

60

80

100

0 50 100 150 200 250 300 350 400 450

Sputter Time (min)

Co

nce

ntr

atio

n (

at%

)

WCOCrFe

Fe

W

Cr

OC

AES profile after 10 min of plasma

Interaction of a-C/W:H with H plasma radicals

Experiments with H2 microwave plasma and concentrated sunlight were performed at the PROMES solar facility in Font-Romeu, France

Pheat = 6 kW Tmax = 850 K Pmw = 1 kW

natom = 2.5×1021 m‑3

P Panjan, MHEST

EU Plasma-Wall Interactions Task ForceSection summarySection summary

Oxygen atoms can remove hydrocarbons effectively in several different experiments

All the evidence indicates that NH3 is more effective for removing hydrocarbons than N2

HCN is the predominant volatile species resulting from removing carbon films

Films containing substitutes for Be for ITER-like trials have been successfully developed


Tokamak cleaning and conditioning techniques


D2

H2

HD

D2-GDCH2-GDC

isotope exchange of D saturated walls by H-GDC → formation of HD

6A H2 + - GDC :→ 1 x 1020 H+/s

→ 1.2 x 1020 HD release (initial)

→ depletion of D

→ increase of H2 release

→ decrease of HD

Quasi saturation after 22 min

= 2.7 1017 H/cm2

2 x 1022 D-atoms released

= 6 x 1016 D/cm2

0 200 400 600 800 1000 12000,0

4,0x1019

8,0x1019

1,2x1020

1,6x1020

HD

rel

ease

( H

D m

ole

cule

s/se

c)

Time (sec)

HDproduction

isotope exchange by GDC

Lost H

14:10 14:20 14:30 14:400,000

0,002

0,004

0,006

0,008

0,010p

ress

ure

(m

bar

)

Time

M2abs M3abs M4abs

Released HD

V Philipps, TEXTOR team


107826: first RF He/H2 after D2-GDC

107828: third shot

107849: first shot after D2-GDC with Bv

107850:second shot with with Bv + Br

0 200,0

5,0x1017

1,0x1018

1,5x1018

2,0x1018

2,5x1018

3,0x1018

3,5x1018

HD

rel

ease

( m

ole

cule

s/s)

Time (s)

Rf pulse

826

828

849

850Smaller initial HD release compared with GDC at the beginning

But HD release increasing shot by shot

Shot to shot variation depends on a complex parameter field: Bt, gas composition, magnetic fields, wall history, .. ..

Comparison: isotope exchange by RF He/H2 ICWC on D saturated walls

All at 2.3T

-5 0 5 10 15 200.00E+000

1.00E-008

2.00E-008

inte

nsi

ty [

A]

time [s]

Schuss109075_M3 Schuss109076_M3 Schuss109077_M3 Schuss109078_M3 Schuss109079_M3 Schuss109080_M3

HD increases in 6 consecutive shots



Overall daily particle balance in He/H2 RF shots on D saturated walls. Hydrogen injection (left scale) is about 10 times hydrogen release from walls (H2 and HD) (right scale). D2 GDC was done at the red arrow marked points. As can be seen, after fresh GDC, the walls tends to saturate shot by shot after, but no saturation is reached in the (3-5 RF) shots. RF shots at low Bt ( blue points) show more hydrogen consumption, since larger areas are wetted by RF

4,0x1019

8,0x1019

1,2x1020

1,6x1020

2,0x1020

107825 107830 107835 107840 1078450,0

4,0x1020

8,0x1020

1,2x1021

1,6x1021

2,0x1021

H-inje

ctio

n (at

om

s)

shot number

Hatomsin

H-e

xhau

st(a

tom

s)

Hatomsout ###

D2 GDC

injectionLow Bt (0.23T)


Overview of 2 days ICWC experiments on TEXTOR


D removal and H implantation during ICWC on Tore Supra

-5 0 5 10 15 200

0.1

0.2

0.3

0.4

0.5

0.6

0.7

time (sec.)

n H/[

n H+

n D]

#43447

#43485

nH/[nH+nD] in ohmic shots (by means of NPA)

after 15+3’ ICWC

Reference ohmicshot before ICWC

-5 0 5 10 15 200

0.1

0.2

0.3

0.4

0.5

0.6

0.7

time (sec.)

n H/[

n H+

n D]

#43447

#43485


-5 0 5 10 15 200

0.1

0.2

0.3

0.4

0.5

0.6

0.7

time (sec.)

n H/[

n H+

n D]

#43447

#43485


after 15+3’ ICWC

Reference ohmicshot before ICWC

0 2 4 6 8 10 12 14 16 18 2010

18

1019

1020

1021

1022

1023

shot number

# p

arti

cles

H injected

H pumpedH impl wall

D pumped

60% H2

30% H2

45% H2

He ICRF

nH/n

D~0,5

nH/n

D~0,04

During ~ 850 sec. of CW ICWC in He-H2 :Total D desorbed : 3,4.1021 D 2 “monolayers”Total H implanted : 3,2.1022 H

Himplanted/Dpumped = 9.4

HDH2HH 2injimplanted

HDD2D 2pumped

After 15 min ICWC in He-H2: nH/(nH+nD) from 5 → 50%

Recovery from disruption after 3 mins pulsed He-ICWC

D Douai, Tore Supra team


Pulsed He-ICWC discharge, duty cycle = 2 sec. ON / 8 sec. OFF

Increase due to summation of aftershot pressure level

Decrease due to wall desaturation (approach to p(H2)= 0)

Duty cycle can be decreased 2:20 or more

Arcing traces on antenna straps: unipolar arcs, plasma between FS and straps - too high RF voltage when operating RF antenna

Pulsed He-ICWC discharges

0 50 100 1500

0.002

0.004

0.006

0.008

0.01

time (sec.)40 45 50 55 60 65 700

0.002

0.004

0.006

0.008

0.01

time (sec.)

TS#43532 PRF~60 kW, ~0,1 Pa

D Douai, Tore Supra team


Both TEXTOR and Tore Supra have devoted campaign days to investigating ICWC during 2009

Both have concentrated on D/H isotope exchange using H2/He ICWC

Resulting wall loading with H has then meant that He discharges have been required for plasma recovery (though relatively easy)

Section summarySection summary


Cleaning gaps and Cleaning gaps and castellationscastellations


WP09-PWI-02-05/MEdC: CLEANING BY A PLASMA TORCH CLEANING BY A PLASMA TORCH FROM INSIDE GAPS FROM INSIDE GAPS

(influence of the geometric aspect ratio of castellated surfaces)

0 1 2 3 4

0.0

0.5

1.0

1.5

2.0

2.5

3.0

Thi

ckne

ss (m

)

Scanned distance (mm)

a-C:H initial thickness = 2.2m

Samples preparation Scanning procedure

Removal conditionsNitrogen flow = 8200 sccmRF power = 350 WDistance from top face of the built castellation = 2mmScanning speed = 5mm/sGap width = 0.5 – 1.5 mm

Results: from profilometryStainless

steel cubesa-C:H layers

Cubes coated with carbon inside gaps (20mm x23mmx20mm)

A stripe of un-deposited layer is defined from top to bottom

Conclusions:Removal of a-C:H layers from inside gaps demonstrated for gap widths 0.5-1.5 mm - Narrower the gap, higher the removal rate - Higher removal rate at the gap entrance- Carbon removal is efficient even on the bottom of the gap (down to 23 mm)

0 1 2

20

15

10

5

0100

50

0

Thickness [m]

Number o

f sca

ns

Ca

ste

llatio

n d

ee

pn

ess

[m

m]

Profile of the remained layer at various scan numbers for gap width 500 microns

Profilometry: film thickness: 2.2 microns

1 scan (4 sec) 46 scans (184 sec) 101 scan (404 s)

Exemple: gap width 500 microns

20/28


tile gaps

decay length: 1.5 times gap width

Erosion of gap structures with remote oxygen GDC

0.01

0.1

1

0 2 4 6 8 10 12 14 16 18

0.5 mm

1 mm

2 mm

4 mm

no

rma

lize

d e

rod

ed

th

ickn

ess

(a

.u.)

remote ECRO

2, 1Pa

270 K48 hours

gap width:

penetration depth (mm)

at 470 K:decay length: several times gap width

at 270 K:

plasma deposited a-C:H

Si

while at 270 K the decay length is too small to be effective it is largely increased at 470 K (larger than for tokamak deposition profiles)

T Schwarz-Selinger and W Jacob, IPP

21/28


300 400 500 6001E-3

0.01

0.1

1

eros

ion

rate

(Å

/ s

ec)

sample temperature (K)

remote ECRO

2, p=1.0 Pa

accessibleto ITER

dir

ect

pla

sma

exp

osu

re:

Å/s

– n

m/s

Erosion of flat substrates with remote oxygen plasmas

erosion of 70 nm hard a-C:H

effective activation energy:0.25 eV

compared to1.3 eV for

thermo-oxidation

erosion rate increases nearly exponential with surface temperature


22/28


Cavity technique: surface loss probabilities β of neutral species

Si s

ubst

rate

s

0 2 4 6 8 10 12 14

0

5

10

15

20

25

10

5

00

25

50

75

100

125

ero

de

d th

ickn

ess

(n

m)

lateral position (mm)

25

nm

6 nm

12

0 n

m

model

= 0.5

remote ECRO

2, 1 Pa

270 K61 hours

(reminder: = 1- reflection)at 270 K: = 0.5

Si s

ubst

rate

s

2 4 6 8 10 12 14

0

10

20

30

40

5020

10

00

10

20

30

40

50

60

70

ero

de

d th

ickn

ess

(n

m)

lateral position (mm)

39

nm

25 nm

55

nm

model

= 0.17

remote ECRO

2, 1 Pa

540 K30 minutes

at 540 K: 0.1

explanation: two different species dominate erosion


EU Plasma-Wall Interactions Task ForceSummary of sectionSummary of section

• Oxygen can only effectively clean Oxygen can only effectively clean gaps and castellations at elevated gaps and castellations at elevated temperaturestemperatures

• The challenge is still to find a The challenge is still to find a method that may work on a practical method that may work on a practical timescale in ITERtimescale in ITER


Laser removal and in-situ Laser removal and in-situ applicationapplication

25/28


26/28


27/28



Rolling from carrier

LASK under vacuum : main issuesLASK under vacuum : main issuesLASK

Carrier

Environment : Very low pressure (10-6Pa)

LASK very exigent with the carrier (Rolling/Pitching & Positioning)

• Scanned area reduction

• Fluence reduction

• Coverage has to be increased

• Limited dust collection efficiency

• Design constraints (laser collimation system size)

An innovative system with limited efficiency

LASK

=> Laser beam inclination requiredand dust collection by adhesion

C Hernandez, CEA


LASK V1

P=10-6Pa T= 200°C max

Environment :

Dust collection : adhesion

LASK V2

P=Atm T= 50°CEnvironment :

Dust collection : aspiration

Improvements to efficiency and vacuum compatibilityImprovements to efficiency and vacuum compatibility

Advantages No vacuum breakNo vacuum breakEfficient dust collectionEfficient dust collectionOptimal laser ablation throughput Optimal laser ablation throughput

Limited dust collection efficiencyLimited dust collection efficiencyLimited laser ablation throughput (tilt Limited laser ablation throughput (tilt effect)effect)

Vacuum breakVacuum breakDisadvantages

C Hernandez, CEA

Diagnostic system Cleaning system

EU Plasma-Wall Interactions Task ForceASDEX sample 041 (graphite with 4m layer of tungsten)

Experimental set-up Nd:YAG laser: 1.063mm, 3.5 ns, 300 mJ, for crater size 1-0.8 mm 13 GW/cm2

Quartz fibre

collimator

tdelay= 100 ns, texp = 500 ns,

Movable holder

Vacuum: 5x10-5 Torr

424 426 428 430 432

3

6

9

Inte

nsi

ty x

104

[a.u

.]

Wavelength [nm]

16 CII

426.73

WI

429.46

P Gasoir, IPPLM

EU Plasma-Wall Interactions Task ForceASDEX sample 041 (graphite with 4m layer of tungsten)

0 2 4 6 8 10 12 14 16

0.0

0.5

1.0

WI 429.46 nm CII 426.73 nm

no

rma

lize

d li

ne

inte

ns

ity

[a

.u.]

number of laser pulse

Line intensity dependence on number of laser pulses

after 4 laser shots Carbon appears, which suggests that during 1 laser pulse 1 m of surface layer is removed continued presence of tungsten for a longer time than expected could be explained by the melting of the metallic tungsten

P Gasoir, IPPLM

EU Plasma-Wall Interactions Task ForceImages of dust generation

Acquisition time: 20 us

Acquisition time: 50 us

Acquisition time: 10 usDelay between laser shot and start of acquisition

~35 us. Best acquisition is with 19 us frame.Most of dust particles are released ~40 us after laser shot.

P Gasoir, IPPLM


Target: Pure graphite plate

slots for TEM nets

holder for a SEM sticker

4 cm

Before exposure After exposure

Dust generation under laser light impact

Collector: Aluminum plate with TEM nets and SEM sticker

Experiment 1 Experiment 2

Number of shots 30 100

Deposited energy/shot

0.76 J 0.33 J

Crater depth 17 µm 24 µm

Crater volume 0.017 mm-3 0.014 mm-3

Ablated material 1.6·1018 atoms 1.28·1018 atoms M Rubel, VR

EU Plasma-Wall Interactions Task ForceMicroscopy after 30 shots @ 0.76 J

TEM nets located near the irradiated spot are destroyed 200 µm

200 µm

2 µm

500 nm

Fine dust (0.5 – 3 m) is generated during graphite irradiation even with laser

pulses of moderate power.

Next step: Irradiation of PFC and probes (incl. NB41) with co-deposits.

M Rubel, VR

EU Plasma-Wall Interactions Task ForceCollection of Dust in TEXTOR

Vacuum cleaning using a cascade set of filters.

• Collection on carbon stickers (adhesive)

• Collection on nets for TEM

• Scraping-off co-deposits from various locations

• Separation of non-magnetic and magnetic fraction.

12

34

56

4

Deposition (1) and erosion (2) zones on ALT; bottom of the liner (3);main poloidal limiters (4); DED bottom shield (5); inner bumper (6)

M Rubel, VR

EU Plasma-Wall Interactions Task ForceFuel in TEXTOR

ALT-II tile

In TEXTOR fuel is mainly retained in flaking co-deposits on the ALT-II limiter tiles.

Therefore, flakes from ALT-II were taken for long-term outgasing:• 70 hours at 573 K• Fast temperature increase to 1273• 1 h at 1273 K

M Rubel, VR

EU Plasma-Wall Interactions Task ForceLong-term Fuel Desorption at 623 K

To determine efficiency of release at maximum baking temperature of ITER divertor

ALT-II: final stage: jump to 1273 K ALT-II: start-up stage 623 K

Release of fuel during the long-term desorption

Heating H2 [%] HD [%] D2 [%]

350 ºC for 3 days 34.1 11.9 5.2

1000 ºC (final stage) 65.9 88.1 94.8Summary: • Only ~10% of D released at 623 K.• Efficient thermal fuel removal requires baking at high temperature.

M Rubel, VR


Laser cleaning has been demonstrated in situ in Tore Supra

Laser cleaning has to be accompanied by dust collection. This is only efficient at atmospheric pressure and low temperature.

Removal of W films on graphite demonstrated.

Dust from tokamaks heated to the ITER vessel temperature will only release ~10% of the contained tritium

Section summarySection summary

EU Plasma-Wall Interactions Task ForceSEWG – Fuel RemovalSEWG – Fuel Removal

Conclusions:Conclusions:

i. All the evidence shows that NH3 is a more effective scavenger than N2, and HCN is the important volatile species

ii. TEXTOR and Tore Supra have each devoted campaign days to development of ICWC

iii. Standard films that simulate likely deposition in ITER (with a replacement for beryllium) have been developed

iv. Consideration is now being given to applicability of chemical and photonic cleaning methods on ITER

v. Removal rates for co-deposit trapped in tile gaps/castellations still require improvement to be applicable

vi. The impact of repetitive oxidising plasmas (GDC/RF) on beryllium bulk, and removal of beryllium oxide have yet to be explored

Baseline Support Summary Table TA: Fuel removal

*)Completed, Partially done, Not done

Task id. Associations involved

Manpower (PPY)

Status*) Short description with milestones/deliverables

WP09-PWI-02-05/CEA/BS

a)Optimisation of Wall Conditioning Techniques in presence of a permanent magnetic field.

b)Characterization of carbon erosion during O2-glow discharges

CEA1.0

0.25

2009 programme completed

Not done

Two days of experimental campaign time on Tore Supra devoted to ICWC

Vessel tank not available

WP09-PWI-02-06/CEA/BS

a)Improve the understanding of the film break-up processes in laser “cleaning”

b)Test of in situ laser layer removal technique in Tore Supra

c)Studies of diags/detri demonstration with remote handling tools (LASK Project)

d)In vessel tritium diagnostic optimisation

CEA1.3

0.5

0.8

0.75

Not done

Completed

2009 programme completed2009 programme completed

No effort available

Integrated with DITS project

Designs of diagnostic and cleaning versions made

Unit can be vacuum, temperature and magnetic field compatible

Baseline Support Summary Table TA: Fuel Removal



Manpower (PPY)

Status*) Short description with milestones/deliverables

WP09-PWI-02-02/CIEMAT/BS CIEMAT 0.7 2009 programme completed

Scavenger experiments

WP09-PWI-02-05/CIEMAT/BS CIEMAT 0.5 Not done Removal of films in gaps and castellations

WP09-PWI-02-02/CNR/BS ENEA-CRN 0.66 2009 programme completed

Scavenger experiments under RF fields

WP09-PWI-02-02/FOM/BS FOM 0.1 Completed Scavenger experiments on PILOT-PSI

WP09-PWI-02-05/FZJ/BS FZJ 0.75 2009 programme completed

2 days ICWC experiments carried out on TEXTOR

IPP 0.5 Not done Problems with Majestix system

WP09-PWI-02-01/IPPLM/BS IPPLM 1.0 Completed Removal of C layers with Al, W

WP09-PWI-02-06/IPPLM/BS IPPLM 1.5 2009 programme completed

Film break-up under laser

WP09-PWI-02-02/IPP/BS

Baseline Support Summary Table TA: Fuel Removal



Manpower (PPY) Status*) Short description with milestones/deliverables

WP09-PWI-02-05/MEdC/BS MEdC 0.75 2009 programme completed

Removal of films in gaps by plasma torch

WP09-PWI-02-01/MHEST/BS MHEST 0.2 Completed Deposition of C(W,Mg) films

WP09-PWI-02-02/MHEST/BS MHEST 0.1 2009 programme completed

WP09-PWI-02-05/MHEST/BS MHEST 0.3 2009 programme completed

Removal of a-C:H films with neutral oxygen

WP09-PWI-02-01/VR/BS VR 0.2 2009 programme completed

Surface analysis before and after fuel removal

eu-pwi tf meeting, warsaw, 4-6 november 2009 fuel removal sewg report 2009 j. p. coad on behalf of...

Documents

h films

h removal

hgdc formation of hd

gdc lost h

mhest slide

nitrogen slide

h plasma radicals experiments

rf plasma nh