Measurements of erosion mechanisms from solid and liquid materials in PISCES-B

Doerner, R.; Baldwin, M.J.; Conn, R.W.; Grossman, A.; Luckhardt, S.; Seraydarian, R.; Tynan, G. R.; Whyte, D.G.

doi:10.1016/s0022-3115(00)00568-7

Cited by 80 publications

(67 citation statements)

References 24 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…It was found, that liquid lithium has an erosion rate higher than what is expected from standard sputtering, such as predicted by the results of Laszlo and Eckstein [10].…”

Section: Introductionmentioning

confidence: 67%

See 1 more Smart Citation

Plasma–lithium interaction in the CDX-U spherical torus

Antar

Doerner

Kaita

et al. 2002

Fusion Engineering and Design

Self Cite

View full text Add to dashboard Cite

Results on the interaction between plasma in the current drive experiment-upgrade (CDX-U) spherical torus and a liquid lithium limiter are reported. It is observed that macroscopic lithium droplets detach from the limiter head and fall towards the plasma core. However, no disruptions occurred during these discharges despite the fact that relatively large-scale blobs are observed entering the confined plasma. A multi-tip Langmuir probe measures the edge plasma properties. It is found that the average density and temperature and their fluctuations are unaffected by the presence of lithium within experimental error.

show abstract

“…It was found, that liquid lithium has an erosion rate higher than what is expected from standard sputtering, such as predicted by the results of Laszlo and Eckstein [10].…”

Section: Introductionmentioning

confidence: 67%

“…The yield per incident ion, estimated by Doerner et al, is about 10% [10]. The number of lithium atoms leaving the droplet due to erosion in 10 ms is thus about 10 16 atoms.…”

Section: Sur6i6al Of Large Lithium Droplets In the Plasmamentioning

confidence: 91%

Plasma–lithium interaction in the CDX-U spherical torus

Antar

Doerner

Kaita

et al. 2002

Fusion Engineering and Design

Self Cite

View full text Add to dashboard Cite

show abstract

“…( [301,477,478]. Spectroscopy is also used to assess the core plasma's impurity contamination [479].…”

mentioning

confidence: 99%

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

et al. 2001

View full text Add to dashboard Cite

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.

show abstract

“…The experiments made on PISCE-B facility demonstrate that the H retention depends also from other impurities [34][35][36].…”

Section: Materials Based On Berylliummentioning

confidence: 94%

A Review of Dangerous Dust in Fusion Reactors: from Its Creation to Its Resuspension in Case of LOCA and LOVA

et al. 2016

View full text Add to dashboard Cite

Abstract:The choice of materials for the future nuclear fusion reactors is a crucial issue. In the fusion reactors, the combination of very high temperatures, high radiation levels, intense production of transmuting elements and high thermomechanical loads requires very high-performance materials. Erosion of PFCs (Plasma Facing Components) determines their lifetime and generates a source of impurities (i.e., in-vessel tritium and dust inventories), which cool down and dilute the plasma. The resuspension of dust could be a consequences of LOss of Coolant Accidents (LOCA) and LOss of Vacuum Accidents (LOVA) and it can be dangerous because of dust radioactivity, toxicity, and capable of causing an explosion. These characteristics can jeopardize the plant safety and pose a serious threat to the operators. The purpose of this work is to determine the experimental and numerical steeps to develop a numerical model to predict the dust resuspension consequences in case of accidents through a comparison between the experimental results taken from campaigns carried out with STARDUST-U and the numerical simulation developed with CFD codes. The authors in this work will analyze the candidate materials for the future nuclear plants and the consequences of the resuspension of its dust in case of accidents through the experience with STARDUST-U.

show abstract

Measurements of erosion mechanisms from solid and liquid materials in PISCES-B

Cited by 80 publications

References 24 publications

Plasma–lithium interaction in the CDX-U spherical torus

Plasma–lithium interaction in the CDX-U spherical torus

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

A Review of Dangerous Dust in Fusion Reactors: from Its Creation to Its Resuspension in Case of LOCA and LOVA

Contact Info

Product

Resources

About