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EU PWI Task Force V. Philipps, SEWG mixed materials, 21.6.06 JET ITER-like Wall Project : Material choice, issues to investigate and role of new SEWG ITER-like.

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Presentation on theme: "EU PWI Task Force V. Philipps, SEWG mixed materials, 21.6.06 JET ITER-like Wall Project : Material choice, issues to investigate and role of new SEWG ITER-like."— Presentation transcript:

1 EU PWI Task Force V. Philipps, SEWG mixed materials, 21.6.06 JET ITER-like Wall Project : Material choice, issues to investigate and role of new SEWG ITER-like Material Mix V. Philipps, J. Roth

2 1700 solid Be tiles machined from 4t of Be Be blanks ordered W coated CFC tiles on high power areas, but 3 cm recessed Be coated Inconel at inner wall cladding NBI Shinethrough protection Inner wall cladding Inner wall guard limiters Upper Dump plates Mushrooms Saddle coil protection Outer and inner poloidal limiters LH + ICRH protection KC1 coil covers B&C tiles Guideline: no carbon in contact with plasma Be first wall Beam shinetrough tiles EU PWI Task Force V. Philipps, SEWG mixed materials, 21.6.06

3 V.Philipps, Seminar IPP, 30_03_06 2. Be melting behaviour: melt layer stability and motion, analysis of molten Be, influence of melting on plasma operation post mortem analysis and wide angle IR post mortem analysis and wide angle IR 3. Fuel retention in (bulk) Be tiles (surface and bulk) post mortem tile analysis 4. Oxidation of Be (leaks, ventings, normal operation), effect on fuel retention, plasma conditioning post mortem analysis, spectroscopy, plasma performance post mortem analysis, spectroscopy, plasma performance 5. Be erosion & redeposition on first wall : characterisation of redeposited Be (mainly on recessed areas of poloidal limiters) post mortem analysis post mortem analysis Full first wall Be : topics to investigate

4 1. Main Wall plasma wall interaction: Be first wall JET Divertor Option 1 20 MJ Option 2 Option 1 A full W divertor will be procured, but JET will preserve 2 options: full W or ITER-like divertor, decision ( or change) can be done on short time schedule 1 3 4 6 7 8 LBSRP Louvers B&C HFGC 5 5a 200μm Plasma sprayed W coating on CFC (tile 1-8) W bulk on tile 5 (LBSRP) High power and ITER-like high triangularity shots outer divertor leg on solid W tiles EU PWI Task Force V. Philipps, SEWG mixed materials, 21.6.06 Divertor

5 Option 1 20 MJ Toroidally isolated EU PWI Task Force V. Philipps, SEWG mixed materials, 21.6.06 W bulk concept (FZ Juelich ) -minimises EM forces and optimise mechanical stability -6mm W-lamellas, poloidal stacks, toroidally isolated

6 V.Philipps, Seminar IPP, 30_03_06 A key question will be: Alloying of Be with W (with possibly some remaining C and O) and consequences for W- erosion With W- bulk lamellas additional key topics can be investigated W-mechanical stability (cracking, fatigue) under repetitive power loads W melt behaviour: melt layer flow, melt layer loss and stability Migration of Be (& C) in W gaps Need coordinated research in EU PWI

7 Tritium retention and material mixings Analysis of fuel retention under new wall conditions is a main goal of the ITER like wall project 1 2 Characteristics of first wall and divertor erosion long and short range material migration (Be versus C) influence of residual C sources and oxygen Should be addressed in both divertor configurations V.Philipps, Seminar IPP, 30_03_06

8 Retention and material mixings (2) Retention and material mixings (2) 1. Fuel retention in Be/C/W/O redeposited mixed layers influence of : composition (in particular C&O ) temperature etc.. 2. Fuel retention in bulk Be (surface and bulk, including oxidation effects) V.Philipps, Seminar IPP, 30_03_06

9 Inner Outer Plasma facing sides: stable Be-C mix (~Be carbide ??) D content : 0.1-0.2 Shadowed areas: more pure C layers D content: 0.4- 1 more information on chemical state of deposits needed & influence of oxygen 1 3 2 6 4 5 1010 7 9 8 MKIIA V.Philipps, Seminar IPP, 30_03_06 M. Rubel et al Present JET conditions

10 10C 1Be Becarbide (?) C layer C Further C- transport by carbon chemistry (?) 1C(?) 10 Be Be 2 W ?? W C ?? New conditions (?) Present conditions Further transport of Be?? (recent PISCES data ) V.Philipps, Seminar IPP, 30_03_06 a-C:H layer

11 MKIIA 67000 sec 1 kg (850 g on divertor floor) EU-PWI-Task Force MKIIGB 58000 sec 600 gC 60 g 116g 170g 100g 480g 8g ~ 1 kg (present estimate, analysis ongoing) MKIISRP 83000 sec, present estimates by myself! T retention is due to large amounts of C- erosion, migration and codeposition ?? (150) erosion Not analysed

12 Massive C sources are needed to produce thick C-deposits leading to large T retention by codeposition 1 kg C = 5 x10 19 C/ 100m 2 = 10 μm on 100 m 2 area Under the new wall conditions, some C source will remain probably originating from: remote areas by H-atom impact, not fully cleaned from C failure of W coatings C impurities in metallic components The residual C can produce C-layers on remote areas in competition with exhaust in form of volatile hydrocarbons estimate of C- exhaust in from of C x H y C5-C14 injected D- atoms: 1800g = 4.8 10 26 D assumed fraction C x H y /D = 1% 4.8 10 24 C x H y ~ 10g C

13 Summary main important open questions, need coordinated research in SEWG - characterise fuel retention in bulk Be tiles (erosion areas) - characterisation of Be redeposition on first wall components (composition and fuel retention) - oxidation/erosion behaviour of large areas of bulk Be and influence on fuel retention - characterisation of Be/W/C/O containing deposits on plasma facing areas, shadowed areas and gaps (divertor region ) - alloying behaviour of Be with W and importance for W erosion behaviour For these topics we should develop physics based understanding to have a solid basis to extrapolate to ITER conditions Needs coordinated work on post mortem analysis of JET tiles, plasma experiments in Pisces and dedicated lab experiments

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