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PWI - related work at VR
Marek Rubel (VR)Projects within ILW : • Beryllium coatings for inner wall cladding (with MEC, UKAEA, FZJ, UCSD, TEKES)
• Development of Beryllium marker tiles (with MEC, UKAEA, UCSD, FZJ )
• Erosion – Deposition diagnostics (with UKAEA, FZJ, IPP, CRPP)
First Mirror Test in EP-1 and EP-2 (with CRPP)
Fuel Inventory, Material Migration and Material Mixing:• Studies of inventory in PFC from JET and TEXTOR (with UKAEA, TEKES, FZJ)
• Tracer Techniques (13C) in material migration studies (with group of Associations)
• In-depth migration of fuel in carbon-based materials (with FZJ, SFA)
• Microanalysis of fuel distribution on PFC (with FZJ, SFA)
• New phase formation on tungsten PFC (with IPPLM, FZJ)
• Deposition and fuel inventory in castellated Be and W tiles (with UKAEA, FZJ)
• Surface state of PFC and dust formation related to fuel removal by oxidation,
annealing and photonic cleaning - laser, flash-light (with FZJ, UKAEA, IPPLM)
2
Be toroidal belt limiter
• Operation: 1989 – 1992
• 56 000 s of plasma
• 2000 castellated blocks.
Studies performed on two tiles:
Castellated grooves: both sides of 6 grooves;
Side surface between the tiles;
Top surfaces of tiles.
Deposition and Fuel Inventory in Castellated Beryllium Limiters from JET
3
Top and Side Surfaces of CleavedBeryllium Limiter Tiles
Cleaved limiter blocks mounted in the chamber for Ion Beam Analysis
4
Deposition in the Castellated Grooves of the Beryllim Limiter Tiles
Side A Side B
Surfaces in thecastellated groove
Freshly cleavedsurface
Freshly cleavedsurface
0
3
6
9
12
15
18
0 3 6 9 12 15
Distance from Plasma [mm]
D a
nd
C [
e17/
cm2]
]
D, Side A
D, Side B
C, Side A
C, Side B
Messages:• Deuterium deposition in the castellation always associated with Carbon
• Short decay lenght of deposition in the castellation: = 1.5 mm.
• D content in the castellated groove does not exceed 7 x 1017 cm-2.
• No deuterium detected in bulk beryllium.
Modelling of transport into castellation is ongoing: CEA, CRPP, FZJ, IPP.CR
5
VERY TENTATIVE scaling to tritium inventory in ITER
Assumptions:
Only 50 % of deuterium remained after 14 years of tile storage(based on studies of carbon PFC after long-term storage in air, M. Rubel)
Deuterium : Tritium retention: 1:1
Area of castellated beryllium tiles: 700 m2
1 ITER shot: 0.5 - 1 year (energy input) or 4 years (fluxes) of JET operation(based on calculations by V. Philipps)
• 0.4 g T / ITER shot (based on energy input)
• 2.3 g T / ITER shot (based on fluxes)
6
Tungsten – Oxygen in castellation of W brush limiter
exposed in TEXTOR
7
Castellated limiter exposed at TEXTOR
8
Castellated limiter exposed at TEXTOR
WWWW WWO WW
W
W
1 2 3 4 5 6 7 8 9 10 11 12
keVFull Scale 292 c ts Cursor: 0.297 (1 cts )
1
WW WW WWW W
W
W
1 2 3 4 5 6 7 8 9 10 11 12
keVFull Scale 226 c ts Cursor: 0.315 (0 cts )
2
Messages:
„Nice design” on the limiter contains W and O.
Very recent result of XRD analysis: WO2. (IPPLM, M. Psoda)
9
Castellated limiter exposed at TEXTOR
WO2 leaves
Questions: Is it a condensed volatile stoichiometric tungsten oxide?If YES, how and why was it formed?What was the source of oxygen? Non-oxygen free Cu?