Tritium inventory and recovery in next-step fusion devices

Causey, R.A.; Brooks, J.N.; Federici, G.

doi:10.1016/s0920-3796(02)00248-x

Cited by 33 publications

(26 citation statements)

References 76 publications

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“…Furthermore, material choice plays a central role in the environmental safety of fusion power reactors in future commercial energy plants [5,6]. A suitable PFM should contain elements of reduced activation in such a way that production of radioactive by products and tritium inventories are minimized [7]. These considerations as well as working condi tions of plasma facing components (PFCs) reduce the availability of material candidates to those based on C, V, W, Ti and Be [8].…”

Section: Introductionmentioning

confidence: 99%

“…Fur thermore, neutron irradiation increases tritium retention on beryllium and carbon base materials, rising safety hazards and reducing environmental attractiveness of fusion power plants due to accidental release of tritium and/or production of hazardous nuclear by products [7]. In addition, low melting point and high toxicity of beryllium have dissuaded about the use of this alloy in fusion reactors.…”

Section: Introductionmentioning

confidence: 99%

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On the oxidation mechanism of pure tungsten in the temperature range 600–800°C

2012

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Abstract:The oxidation behavior of International Thermonuclear Experimental Reactor (ITER) reference tungsten grade has been evaluated in dry air in the temperature range 600 800 °C. At 600 °C, the scale remained protective while the integrity of W 18 O 49 layer was kept. Rapid increase in mass gain resulted from mas sive cracking at local areas in the W 18 O 49 layer. Then, a coarse non protective columnar WO 2.92 scale was developed which favoured rapid inward oxygen transport into the alloy. At 700 and 800 °C, growth stres ses in the scale were released through local cracking. At this stage, WO 2.92 became progressively trans formed into WO 3 when the oxygen partial pressure increased across the scale thickness.

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Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

On the oxidation mechanism of pure tungsten in the temperature range 600–800°C

2012

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“…With this choice, erosion and redeposition of carbon accompanied by codeposition of hydrogen isotopes is expected to be one of the dominant tritium retention mechanisms [1][2][3]. As there will be strict safety limits, control of the tritium inventory will be mandatory.…”

Section: Introductionmentioning

confidence: 99%

Oxygen glow discharge cleaning in nuclear fusion devices

Hopf

Jacob

Rohde

2008

Journal of Nuclear Materials

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Laboratory experiments were carried out as part of the preparations of an oxygen glow discharge cleaning experiment in ASDEX Upgrade. They aimed at evaluating the effect of mixing the oxygen with helium, the collateral damage caused by the glow discharge, as well as the influence of impurities in the films being eroded. Oxygen concentrations below 20 % in helium are sufficient to achieve high erosion rates. The discharge can lead to the formation of oxide layers on surfaces which-as demonstrated for tungsten-can be rapidly reduced by post-treatment in a hydrogen discharge. For carbon, aluminum and iron the physical sputtering yield may become similar to the erosion yield of redeposited layers, but it is by more than one order of magnitude smaller for tungsten. Using a-B:C:H films with varying boron content, it was found that impurities can cause the erosion rate to drop by orders of magnitude.

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“…2). It should be noted here that in earlier publications of Vietzke et al [15,16] 4 contribute about 35% to the total erosion yield. In fact, the yields in Refs.…”

Section: Resultsmentioning

confidence: 53%

“…In the present design for ITER it is also foreseen to build parts of the divertor-the strike zone-from CFC (carbon fiber composites) material [1,2]. With this choice, erosion and redeposition of carbon accompanied by co-deposition of hydrogen isotopes is expected to be one of the dominant tritium retention mechanisms [1,3,4].…”

Section: Introductionmentioning

confidence: 99%

Temperature dependence of the chemical sputtering of amorphous hydrogenated carbon films by hydrogen

Schlüter

Hopf

Schwarz-Selinger

et al. 2008

Journal of Nuclear Materials

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The temperature dependence of chemical erosion and chemical sputtering of amorphous hydrogenated carbon films due to exposure to hydrogen atoms (H 0 ) alone and combined exposure to argon ions and H 0 was measured in the temperature range from 110 to 950 K. The chemical erosion yield for H 0 alone is below the detection limit for temperatures below about 340 K. It increases strongly with increasing temperature, goes through a maximum around 650 to 700 K and decreases again for higher temperatures. Combined exposure to Ar + and H 0 results in substantial chemical sputtering yields in the temperature range below 340 K. In this range the yield does not depend on temperature, but it increases with energy from about 1 (eroded carbon atoms per impinging Ar + ion) to about 4 if the ion energy is increased from 50 to 800 eV. For temperatures above 340 K the measured erosion rates show the same temperature dependence as for the H 0 -only case, but they are higher than for H 0 -only. The difference between the Ar + and H 0 and the H 0 -only cases increases monotonically with increasing ion energy.

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Tritium inventory and recovery in next-step fusion devices

Cited by 33 publications

References 76 publications

On the oxidation mechanism of pure tungsten in the temperature range 600–800°C

On the oxidation mechanism of pure tungsten in the temperature range 600–800°C

Oxygen glow discharge cleaning in nuclear fusion devices

Temperature dependence of the chemical sputtering of amorphous hydrogenated carbon films by hydrogen

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