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1. Material transport from marker tiles in the JET divertor

2. Overview of damage to beryllium limiters by unmitigated disruptions and runaway electrons in the JET tokamak with metal walls

3. Reassessment of tritium content in CFC tiles exposed to the JET D-T campaign in 1997

4. Comparison of JET inner wall erosion in the first three ITER-like wall campaigns

5. Fuel desorption from JET-ILW materials: assessment of analytical approach and identification of sources of uncertainty and discrepancy

6. Deposition of impurity metals during campaigns with the JET ITER-like Wall

7. Overview of the JET ITER-like wall divertor

8. Deuterium retention in the divertor tiles of JET ITER-Like wall

9. Assessment of erosion, deposition and fuel retention in the JET-ILW divertor from ion beam analysis data

10. Deuterium retention on the tungsten-coated divertor tiles of JET ITER-like wall in 2015–2016 campaign

11. Comparison of JET inner wall erosion in the first three ITER-like wall campaigns

12. Fuel inventory and material migration of JET main chamber plasma facing components compared over three operational periods

13. Measurement of dust conversion factor for the JET carbon divertor phases

14. Deposition in the tungsten divertor during the 2011–2016 campaigns in JET with ITER-like wall

15. Local deposition of 13C tracer in the JET MKII-HD divertor

16. Overview of the JET results in support to ITER

17. Performances of Rh and Mo mirrors under JET exposure

18. Surface compositional study of Be and T contaminated CFC tiles from JET

19. Structural changes and distribution of accumulated tritium in the carbon based JET tiles

20. Fusion Technology related studies at JET

21. Erosion and re-deposition processes in JET tiles studied with ion beams

22. First Mirrors Test in JET for ITER

23. Temperature dependence of D removal from JET codeposits by thermo-oxidation

24. Appearance of hot spots due to deposits in the JET MKII-HD outer divertor

25. Assessment of the flash-lamp photon-cleaning detritiation method tested at JET

26. Erosion and deposition behaviour of a-C:H layers in the private flux region of the JET MKII-HD divertor

27. Preliminary assessment of possible carbide formation on Be and T contaminated CFC tiles from JET

28. Testing of beryllium marker coatings in PISCES-B for the JET ITER-like wall

29. Overview of long-term fuel inventory and co-deposition in castellated beryllium limiters at JET

30. Ex-situ tritium removal from JET tiles using RF inductive heating

31. Structural investigation of re-deposited layers in JET

32. Thermal release rate of tritium trapped in bulk and plasma exposed surfaces of carbon specimens obtained from JET divertor

33. Tritium distribution measurement of JET Mk II SRP divertor tiles

34. Post mortem analysis of a JET quartz microbalance system

35. Erosion and deposition in the JET MkII-SRP divertor

36. Nuclear reaction analysis with ion microbeam of cross sections of surface layers deposited in a tokamak divertor

37. Characterization and heat flux testing of beryllium coatings on Inconel for JET ITER-like wall project

38. Efficacy of photon cleaning of JET divertor tiles

39. Preliminary Monte Carlo simulation of beryllium migration during JET ITER-like wall divertor operation

40. Detailed Tritium Distribution on the JET MK IIA Divertor Tiles

41. Tritium Retention in the Gap between the Plasma-Facing Carbon Tiles Used in D-T Discharge Phase in JET and TFTR

42. Accelerator-based ion beam analysis of fusion reactor materials

43. Effect of plasma configuration on carbon migration measured in the inner divertor of JET using quartz microbalance

44. Characterisation of flakes generated in JET after DD and DT plasma operations

45. Post-mortem measurements of fuel retention at JET in 2007–2009 experimental campaign

46. Overview of tracer techniques in studies of material erosion, re-deposition and fuel inventory in tokamaks

47. Modelling of carbon transport in fusion devices: evidence of enhanced re-erosion of in-situ re-deposited carbon

48. Tritium inventory control—the experience with DT tokamaks and its relevance for future machines

49. Beryllium and carbon films in JET following D–T operation

50. Tritium removal from JET and TFTR tiles by a scanning laser

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