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Behavio u r of tritium accumulated in the surface layer of beryllium tiles

Behavio u r of tritium accumulated in the surface layer of beryllium tiles. E. Kolodinska 1 , G. Ķizāne 1 , J.P.Coad 2 , A. Vītiņš 1 , V. Tīlika 1 , I. Dušenkova 1

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Behavio u r of tritium accumulated in the surface layer of beryllium tiles

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  1. Behaviour of tritium accumulated in the surface layer of beryllium tiles E. Kolodinska1, G. Ķizāne1, J.P.Coad2, A. Vītiņš1, V. Tīlika1, I. Dušenkova1 1 Laboratory of Solid State Radiation Chemistry, Institute of Chemical Physics University of Latvia, Kronvalda blvd. 4, Latvia, elina.kolodinska@lu.lv 2 Culham Science Centre, EURATOM UKAEA Fusion Association, Abingdon, UK 9th International Workshop on Hydrogen Isotopes in Fusion Reactor materials, Salamanca, Spain, June 2 -3, 2008

  2. Outline • Samples • Methods • Tritium distribution in depth of beryllium surface and deposition layer • Chemical forms of tritium and chemical composition of deposition layer • Changes of beryllium structure after exposure in plasma chamber • Tritium release under different conditions • Summary 9th International Workshop on Hydrogen Isotopes in Fusion Reactor materials, Salamanca, Spain, June 2 -3, 2008

  3. Samples • 2 Upper belt limiter beryllium tiles (A and B) exposed in the Joint European Torus (JET) during D + D and D + T experiments in 1989 – 1994 • Tile A tritium activity 10 – 60 kBq·cm-2 • Tile B tritium activity 2.4 – 4.8 kBq·cm-2 • Toroidal limiter beryllium tile – un-exposed 9th International Workshop on Hydrogen Isotopes in Fusion Reactor materials, Salamanca, Spain, June 2 -3, 2008

  4. Methods • Lyo-method (tritium chemical forms and distribution) The method is based on beryllium dissolution process and tritium reactions with chemical scavengers (tritium detection – gas flow detector, liquid scintilation detector). • Beo + 2H+ Be2+ + 2Ho • Ho +Ho H2(g) K~1.1010mol-1 s-1 • Ho +To HT (g) K~1.1010mol-1 s-1 • To +To T2(do not occur, because [To] ,< 10-6 M) • T2 (s) T2(g) • T+(s) T+(liq) • A sum=(AT2 +ATo)g+ AT+liq • 6Ho +Cr2O7-2+4H2SO4SO42- + Cr2 (SO4) 3 + 7H2O K=2.6.1010 mol-1 s-1 • Asum =(AT2 +(1-x) ATo)g + ( AT+ + x ATo)liq • Scanning Electron Microscopy SEM(surface structure, grain sizes) • (Hitachi S-4800 and JSM 6490 ) • in addition of • Energy Dispersive X-ray detection EDX (chemical impurities)(EDAX Sapphire Si(Li) Detecting Unit with Ultra Thin window technology, for superior light element analysis down to Beryllium ) 9th International Workshop on Hydrogen Isotopes in Fusion Reactor materials, Salamanca, Spain, June 2 -3, 2008

  5. Methods Tritium monitor behind safety wall • Thermoannealing in the Radiation Thermomagnetic Rig under different conditions (tritium release) • Temperature (773 K, constant rate 5K·min-1 ) • Temperature and radiation (accelerated electrons (E=5MeV) radiation of 14MGy·h-1) • Temperature and magnetic field (1.7 – 2.35 T) • Simultaneous action of all three factors: temperature, radiation, magnetic field Thermomagnetic rigon the basis of electron accelerator LINAC-4 9th International Workshop on Hydrogen Isotopes in Fusion Reactor materials, Salamanca, Spain, June 2 -3, 2008

  6. Distribution of tritiumin the surface of beryllium tiles Tritium in upper belt limiter Be tile was found in the surface layer up to 150mm with maximum concentration at 10-40 mm from the surface 9th International Workshop on Hydrogen Isotopes in Fusion Reactor materials, Salamanca, Spain, June 2 -3, 2008

  7. Thickness of deposited layer on the surface of upper limiter beryllium tiles The thickness of deposited layer on upper belt limiter beryllium tile has been found to be in range from 10 – 35 mm (average thickness ~ 20 mm ) Cross-section of beryllium tile Structure of beryllium – deposited layer boundary 9th International Workshop on Hydrogen Isotopes in Fusion Reactor materials, Salamanca, Spain, June 2 -3, 2008

  8. Scheme of distribution of tritium against thickness of deposited layer Intensity of red colour corresponds to the amount of tritium (darker regions correspond to higher tritium concentration) Highest concentration of accumulated tritium was found at the boundary between beryllium and deposited layer. 9th International Workshop on Hydrogen Isotopes in Fusion Reactor materials, Salamanca, Spain, June 2 -3, 2008

  9. Chemical forms of tritium in different parts of the surface of beryllium tiles (B tile) Operating surface Lateral surface Lateral surface between teeth (castellation) Melted surface 9th International Workshop on Hydrogen Isotopes in Fusion Reactor materials, Salamanca, Spain, June 2 -3, 2008

  10. Chemical composition of surface of beryllium tile (non-melted and melted parts) Non-melted Melted 9th International Workshop on Hydrogen Isotopes in Fusion Reactor materials, Salamanca, Spain, June 2 -3, 2008

  11. Chemical composition of surface and tritium chemical forms In the melted parts of beryllium surface tritium was found mostly as T+. In non-melted areas there were found all three chemical forms of tritium : T2 (47-73%), To (16-25%), T+ (11-33%). In the melted parts up to 66 wt% oxygen was found, that could form a chemical bond with tritium OT-. Non-melted parts mostly contains beryllium, but beryllium tritide is not stable at the temperatures of plasma chamber wall 9th International Workshop on Hydrogen Isotopes in Fusion Reactor materials, Salamanca, Spain, June 2 -3, 2008

  12. Changes of beryllium structure Surface of un-exposed beryllium tile Distribution of grain sizes has been estimated both on exposed and un-exposed beryllium tiles. Average grain size for un-exposed beryllium is 3.5 mm, but for exposed – 6.5 mm. The increase of grain size of beryllium material has been observed after exposure in plasma chamber by factor ~2 9th International Workshop on Hydrogen Isotopes in Fusion Reactor materials, Salamanca, Spain, June 2 -3, 2008

  13. Tritium release Tritium diffusion (release) efficiency depends on grain size, impurities and structure defects During the exposure in plasma chamber the structure of beryllium changes, growth of grains occurs. 9th International Workshop on Hydrogen Isotopes in Fusion Reactor materials, Salamanca, Spain, June 2 -3, 2008

  14. Tritium release by thermoannealing The effect of different factors on tritium release depends on properties of sample. Tiles A and B have different initial distribution of chemical forms of tritium ( in the B tile there is more T+ form than in the A tile) and structure (grain size, impurities, dislocations, etc.). 9th International Workshop on Hydrogen Isotopes in Fusion Reactor materials, Salamanca, Spain, June 2 -3, 2008

  15. Summary • Most tritium accumulated in the beryllium tiles was found on the boundary of deposited layer and beryllium • Distribution of tritium chemical forms depends on chemical composition of surface layer, and it is different in areas that have been melted by the plasma • Changes of beryllium structure after exposure in plasma chamber have been observed, grain size has grown by factor 2. • The facilitating effect of tritium release under simultaneous action of temperature, radiation and magnetic field observed previously depends on the properties of particular sample. 9th International Workshop on Hydrogen Isotopes in Fusion Reactor materials, Salamanca, Spain, June 2 -3, 2008

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