1. 1 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 ( 13 C) 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. 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. 3 Top and Side Surfaces of Cleaved Beryllium Limiter Tiles Cleaved limiter blocks mounted in the chamber for Ion Beam Analysis

4. 4 Deposition in the Castellated Grooves of the Beryllim Limiter Tiles Side ASide B Surfaces in the castellated groove Freshly cleaved surface Freshly cleaved surface 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 10 17 cm -2. No deuterium detected in bulk beryllium. Modelling of transport into castellation is ongoing: CEA, CRPP, FZJ, IPP.CR

5. 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 m 2 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. 6 Tungsten – Oxygen in castellation of W brush limiter exposed in TEXTOR

7. 7 Castellated limiter exposed at TEXTOR

8. 8 Messages: Nice design on the limiter contains W and O. Very recent result of XRD analysis: WO 2. (IPPLM, M. Psoda)

9. 9 Castellated limiter exposed at TEXTOR WO 2 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?