Status and physics basis of the ITER divertor

Pitts, R.A.; Kukushkin, A. S.; Loarte, A.; Martín, A.; Merola, M.; Kessel, C.; Komarov, V.; Shimada, M.

doi:10.1088/0031-8949/2009/t138/014001

Cited by 182 publications

(146 citation statements)

References 23 publications

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“…4) and higher temperature. The first wall and the divertor area of the ITER vacuum vessel will be baked at 515 K and 623 K, 5 respectively, in the range of temperature in which beryllium carbide is expected to be formed. The formation of mixed Be/C materials was also investigated in the PIESCES-B facility.…”

Section: Introductionmentioning

confidence: 99%

Absorption and diffusion of beryllium in graphite, beryllium carbide formation investigated by density functional theory

Ferro

Allouche

Linsmeier

2013

Journal of Applied Physics

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The formation of beryllium carbide from beryllium and graphite is here investigated. Using simple models and density functional theory calculations, a mechanism leading to beryllium carbide is proposed; it would be (i) first diffusion of beryllium in graphite, (ii) formation of a metastable beryllium-intercalated graphitic compound, and (iii) phase transition to beryllium carbide. The growth of beryllium carbide is further controlled by defects' formations and diffusion of beryllium through beryllium carbide. Rate limiting steps are the formation of defects in beryllium carbide, with estimated activation energies close to 2 eV. V C 2013 AIP Publishing LLC.

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Section: Introductionmentioning

confidence: 99%

Absorption and diffusion of beryllium in graphite, beryllium carbide formation investigated by density functional theory

Ferro

Allouche

Linsmeier

2013

Journal of Applied Physics

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“…The foreseen annealing temperature of the first wall is 500 K [6]. Section 3 is dedicated to the efficiency of this annealing temperature in removing D after implantation to high fluences.…”

Section: Introductionmentioning

confidence: 99%

Deuterium release from implanted beryllium and beryllium oxide

Oberkofler

Linsmeier

2011

Journal of Nuclear Materials

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The retention and release of deuterium is compared for clean metallic beryllium and beryllium oxide. Deuterium energies of 600 eV per atom are applied and implantation fluences are above the threshold for supersaturation. Desorption experiments subsequent to implantation into metallic Be are extrapolated to a perfectly homogeneous implantation spot. It is assessed that more than 80 % of the D retained after implantation with homogeneous high fluences are released below 500 K. All retained D is released below 800 K. The oxide layer is grown by stepwise oxidation of Be in oxygen atmosphere and characterized by Rutherford backscattering spectrometry.The oxide thickness is large enough to guarantee deuterium implantation completely within the oxide layer. The release of deuterium from BeO proceeds at a slow rate over the whole temperature range from 350 to 850 K.At this temperature only 75 % of the amount retained after implantation has desorbed.

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“…The interest in tungsten spectra is spurred by the design choice of 3 the heavy element as a plasma-facing material in the ITER divertor [1] due to its favorable physical and chemical 4 properties: it has a high melting point, low sputtering yields, high-energy sputtering threshold, and low tritium 5 retention. On the agenda for several present-day fusion machines is to operate with tungsten components to learn 6 machine behavior and study the effects of tungsten-seeded plasmas.…”

mentioning

confidence: 99%

Atomic data of tungsten for current and future uses in fusion and plasma science

Clementson

Beiersdörfer

Lennartsson

2013

AIP Conference Proceedings

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Abstract. Atomic physics has played an important role throughout the history of experimental plasma 5 physics. For example, accurate knowledge of atomic properties has been crucial for understanding the plasma 6 energy balance and for diagnostic development. With the shift in magnetic fusion research toward high-7 temperature burning plasmas like those expected to be found in the ITER tokamak, the atomic physics of 8 tungsten has become of importance. Tungsten will be a constituent of ITER plasmas because of its use as a 9 plasma-facing material able to withstand high heat loads with lower tritium retention than other possible 10 materials. Already, ITER diagnostics are being developed based on using tungsten radiation. In particular, 11 the ITER Core Imaging X-ray Spectrometer (CIXS), which is designed to measure the core ion temperature 12 and bulk plasma motion, is being based on the x-ray emission of neonlike tungsten ions (W 64+ ). In addition, 13 tungsten emission will at ITER be measured by extreme ultraviolet (EUV) and optical spectrometers to 14 determine its concentration in the plasma and to assess power loss and tungsten sputtering rates. On present-

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Status and physics basis of the ITER divertor

Cited by 182 publications

References 23 publications

Absorption and diffusion of beryllium in graphite, beryllium carbide formation investigated by density functional theory

Absorption and diffusion of beryllium in graphite, beryllium carbide formation investigated by density functional theory

Deuterium release from implanted beryllium and beryllium oxide

Atomic data of tungsten for current and future uses in fusion and plasma science

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