Erosion of beryllium and deposition of carbon and oxygen due to bombardment with C+ and CO+ ions

Goldstrass, P.; Eckstein, W.; Linsmeier, Ch.

doi:10.1016/s0022-3115(98)00545-5

Cited by 10 publications

(10 citation statements)

References 12 publications

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“…Once the surface recession rate is reduced more carbon will build up in the implantation zone and eventually a carbon rich layer results. Calculations based on this mathematical expression for the surface binding energy do a good job of replicating ion beam sputtering results [38,39]. Similar behavior is predicted for Be ions impinging on a carbon target [40].…”

Section: Beryllium/carbon Systemsupporting

confidence: 57%

“…In measurements involving the tertiary mixed-material Be-C-O system, dramatically different results are obtained. Recall that the interaction of the two-component Be-C system resulted in the formation of a Be 2 C layer, the bombardment of beryllium with CO + ion beams results in almost exclusive binding of the beryllium to the oxygen in the implantation zone [35,39]. The carbon atoms present are then bound up in C-C or C-O bonds.…”

Section: Beryllium/carbon Systemmentioning

confidence: 99%

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The implications of mixed-material plasma-facing surfaces in ITER

Doerner

2007

Journal of Nuclear Materials

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Section: Beryllium/carbon Systemsupporting

confidence: 57%

Section: Beryllium/carbon Systemmentioning

confidence: 99%

The implications of mixed-material plasma-facing surfaces in ITER

Doerner

2007

Journal of Nuclear Materials

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“…Carbon chemical erosion can be drastically reduced by impurities on the surface [405] and in the bulk [406]. Surface impurities, such as incident Be ions on the ITER C target can reduce the chemical erosion of carbon by coverage effects [405,407].…”

Section: Effects Of Materials Mixing On Erosionmentioning

confidence: 99%

Chapter 4: Power and particle control

Loarte¹,

et al. 2007

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Abstract.Progress, since the ITER Physics Basis publication, in understanding the processes that will determine the properties of the plasma edge and its interaction with material elements in ITER is described. Experimental areas where significant progress has taken place are : energy transport in the SOL in particular of the anomalous transport scaling, particle transport in the SOL that plays a major role in the interaction of diverted plasmas with the main chamber material elements, ELM energy deposition on material elements and the transport mechanism for the ELM energy from the main plasma to the plasma facing components, the physics of plasma detachment and neutral dynamics including the edge density profile structure and the control of plasma particle content and He removal, the erosion of low and high Z materials in fusion devices, their transport to the core plasma and their migration at the plasma edge including the formation of mixed materials, the processes determining the size and location of the retention of tritium in fusion devices and methods to remove it and the processes determining the efficiency of the various fuelling methods as well as their development towards the ITER requirements. This experimental progress has been accompanied by the development of modelling tools for the physical processes at the edge plasma and plasma-materials interaction and the further validation of these models by comparing their predictions with the new experimental results. Progress in the modelling development and validation has been mostly concentrated in the following areas : refinement of the predictions for ITER with plasma edge modelling codes by inclusion of detailed geometrical features of the divertor and the introduction of physical effects, which can play a 2 major role in determining the divertor parameters at the divertor for ITER conditions such as hydrogen radiation transport and neutral-neutral collisions, modelling of the ion orbits at the plasma edge, which can play a role in determining power deposition at the divertor target, models for plasma-materials and plasma dynamics interaction during ELMs and disruptions, models for the transport of impurities at the plasma edge to describe the core contamination by impurities and the migration of eroded materials at the edge plasma and its associated tritium retention and models for the turbulent processes that determine the anomalous transport of energy and particles across the SOL. The implications for the expected performance of the reference regimes in ITER, the operation of the ITER device and the lifetime of the plasma facing materials are discussed. Introduction.This chapter outlines the significant progress achieved since the ITER Physics Basis in understanding basic scrape-off layer (SOL) and divertor processes in a tokamak. The interaction of plasma with first-wall surfaces will have considerable impact on the performance of fusion plasmas, the lifetime of plasma facing components, and the retention of tritium in next step Burning Plasma E...

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“…The systems C + and CO + on Be [338] and C + and CH One important parameter is certainly the carbon concentration in the incident ion flux [335]. The transition from erosion to deposition occurs at lower ion energies as the carbon concentration decreases (Sect.…”

Section: Erosion Data Of Mixed-materialsmentioning

confidence: 99%

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

et al. 2001

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The major increase in discharge duration and plasma energy in a next step DT fusion reactor will give rise to important plasma-material effects that will critically influence its operation, safety and performance. Erosion will increase to a scale of several centimetres from being barely measurable at a micron scale in today's tokamaks. Tritium co-deposited with carbon will strongly affect the operation of machines with carbon plasma facing components. Controlling plasma-wall interactions is critical to achieving high performance in present day tokamaks, and this is likely to continue to be the case in the approach to practical fusion reactors. Recognition of the important consequences of these phenomena stimulated an internationally co-ordinated effort in the field of plasma-surface interactions supporting the Engineering Design Activities of the International Thermonuclear Experimental Reactor project (ITER), and significant progress has been made in better understanding these issues. The paper reviews the underlying physical processes and the existing experimental database of plasma-material interactions both in tokamaks and laboratory simulation facilities for conditions of direct relevance to next step fusion reactors. Two main topical groups of interaction are considered: (i) erosion/redeposition from plasma sputtering and disruptions, including dust and flake generation and (ii) tritium retention and removal. The use of modelling tools to interpret the experimental results and make projections for conditions expected in future devices is explained. Outstanding technical issues and specific recommendations on potential R&D avenues for their resolution are presented.

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Erosion of beryllium and deposition of carbon and oxygen due to bombardment with C+ and CO+ ions

Cited by 10 publications

References 12 publications

The implications of mixed-material plasma-facing surfaces in ITER

The implications of mixed-material plasma-facing surfaces in ITER

Chapter 4: Power and particle control

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

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