Transmutation of plasma facing materials by the neutron flux in a DT fusion reactor

Behrisch, R.; Khripunov, V.I.; Santoro, R.T.; Yesil, J. M.

doi:10.1016/s0022-3115(98)00249-9

Cited by 12 publications

(6 citation statements)

References 20 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…This has been observed experimentally in thermal and fast fission reactor testing, and fairly reliable calculations have been made for representative fusion applications [905,906]. A major outstanding issue for most materials, especially Be, is the influence of neutron damage on trapping.…”

Section: Modelling Approachesmentioning

confidence: 84%

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

Section: Modelling Approachesmentioning

confidence: 84%

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

et al. 2001

View full text Add to dashboard Cite

show abstract

“…Due to scattering and nuclear reactions in the vessel wall material and the blanket surrounding the vessel wall the total neutron flux is expected to be about a factor 100 higher, a distribution calculated for ITER is shown in Fig. 20 [96].…”

Section: Erosion At the Vesselmentioning

confidence: 99%

Plasma-facing materials for fusion devices

Behrisch¹

2010

J. Synch. Investig.

View full text Add to dashboard Cite

“…A further consideration, at least for beryllium in tokamak applications, is the production of helium and tritium by neutronic transmutations in the beryllium itself. This has been observed experimentally in thermal and fast fission reactor testing, and fairly reliable calculations have been made for representative fusion applications [905,906]. A major outstanding issue for most materials, especially Be, is the influence of neutron damage on trapping.…”

Section: Status Of Model Validationmentioning

confidence: 84%

Plasma-material Interactions in Current Tokamaks and their Implications for Next-step Fusion Reactors

Federici¹,

Skinner²,

Brooks³

et al. 2001

View full text Add to dashboard Cite

This Max-Planck-Institut für Plasmaphysik (IPP), Garching, Germany, report is intended for internal use. IPP reports express the views of the authors at the time of writing and do not necessarily reflect the opinions of the Max-Planck-Institut für Plasmaphysik or the final opinion of the authors on the subject. Neither the Max-Planck-Institut für Plasmaphysik, nor the Euratom Commission, nor any person acting on behalf of either of these: (1) gives any guarantee as to the accuracy and completeness of the information contained in this report, or that the use of any information, apparatus, method or process disclosed therein may not constitute an infringement of private owned right; or (2) assumes any liability for damage resulting from the use of any information, apparatus, method or process in this report.

show abstract

Transmutation of plasma facing materials by the neutron flux in a DT fusion reactor

Cited by 12 publications

References 20 publications

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

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

Plasma-facing materials for fusion devices

Plasma-material Interactions in Current Tokamaks and their Implications for Next-step Fusion Reactors

Contact Info

Product

Resources

About