Sputtering erosion of beryllium coated plasma facing components—general considerations and analysis for ITER detached plasma regime

Brooks, J.N.; Ruzic, D. N.; Hayden, D. B.

doi:10.1016/s0920-3796(97)00090-2

Cited by 20 publications

(8 citation statements)

References 24 publications

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“…[153,157,848]). Using worst-case (coldest) surface temperatures for the critical beryllium deposition zones of ≈500 K, tritium co-deposition rates for beryllium are estimated by Brooks et al to be ≈0.1 g/pulse, using low-oxygen-content Causey et al H/Be trapping data [469], or ≈0.6 g/pulse, using "carbon-corrected" Mayer et al data [470].…”

Section: (January 2001)mentioning

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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Section: (January 2001)mentioning

confidence: 99%

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

et al. 2001

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“…At low and intermediate collision energies below the ion dissociation limit, the colliding electron may transfer its kinetic energy to the vibrational motion of the BeH + ion and then, may be temporarily captured into a bound Rydberg state of the neutral, BeH * , as described by equations [(11-14)]. This bound state is predissociated by dissociative states BeH * * due to the Rydberg-valence interaction [equation (7)], resulting in the total (direct and indirect) mechanism [equations (4) and (5)]. In Fig.…”

Section: Dissociative Recombinationmentioning

confidence: 99%

“…Beryllium has been proposed as a plasma facing material candidate in the edge of the International Thermonuclear Experimental Reactor (ITER) [1] in order to suppress chemical erosion of carbon in the main chamber [2]. The choice of beryllium is justified by its small impact on the plasma performance [3] since it should have a low tritium retention [4,5]. The beryllium wall will be exposed to plasma heat and particles bombardment at the edge of the reactor and then it will undergo chemical erosion [4,6,7].…”

Section: Introductionmentioning

confidence: 99%

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Multichannel-quantum-defect-theory treatment of reactive collisions between electrons and BeH+

Niyonzima

Lique

Chakrabarti³

et al. 2013

Phys. Rev. A

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A theoretical treatment of dissociative recombination (DR), vibrational excitation (VE) and vibrational deexcitation (VdE) of the BeH + ion in its four lowest vibrational states (X 1 Σ + , v + i = 0, 1, 2, 3) is reported. The multichannel quantum defect theory is used to determine cross sections and rate coefficients. Three electronic symmetries of BeH-2 Π, 2 Σ + , and 2 ∆-have been included in the calculations. At low energies the DR is dominated by capture into states of 2 Π symmetry. Satisfactory agreement with results obtained using the wave packet approach is reached at intermediate energies despite significant differences at low energies. Cross sections and rate coefficients suitable for the modeling of the kinetics of BeH + in fusion plasmas and in the stellar atmospheres are presented and discussed.

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“…Even though various isotopes of light elements can be coupled to achieve thermonuclear fusion energy release, the next generation of thermonuclear fusion reactors will use deuterium-tritium (D-T) reactions, by far most efficient and accessible plasma fuel for fusion reactors and power plants. As discussed in detail elsewhere [1,2,3,4,5,6], beryllium (Be) is meant to enter the composition of the wall of the future fusion devices (ITER). Its performance on preventing tritium retention and, meanwhile, still keeping the benefits of a low Z material (low fuel dilution), is currently being tested in the JET [3,4].…”

Section: Introductionmentioning

confidence: 99%

Theoretical resonant electron-impact vibrational excitation, dissociative recombination and dissociative excitation cross sections of ro-vibrationally excited BeH⁺ ion

Laporta

Chakrabarti²,

Celiberto

et al. 2017

Plasma Phys. Control. Fusion

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We provide cross sections and Maxwell rate coefficients for reactive collisions of slow electrons with BeH + ions on all the eighteen vibrational levels (X 1 Σ + , v + i = 0, 1, 2,. .. , 17) using a Multichannel Quantum Defect Theory (MQDT)-type approach. These data on dissociative recombination, vibrational excitation and vibrational de-excitation are relevant for magnetic confinement fusion edge plasma modelling and spectroscopy, in devices with beryllium based main chamber materials, such as the International Thermonuclear Experimental Reactor (ITER) and the Joint European Torus (JET). Our results are presented in graphical form and as fitted analytical functions, the parameters of which are organized in tables.

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Sputtering erosion of beryllium coated plasma facing components—general considerations and analysis for ITER detached plasma regime

Cited by 20 publications

References 24 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

Multichannel-quantum-defect-theory treatment of reactive collisions between electrons and BeH+

Theoretical resonant electron-impact vibrational excitation, dissociative recombination and dissociative excitation cross sections of ro-vibrationally excited BeH⁺ ion

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Sputtering erosion of beryllium coated plasma facing components—general considerations and analysis for ITER detached plasma regime

Cited by 20 publications

References 24 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

Multichannel-quantum-defect-theory treatment of reactive collisions between electrons and BeH+

Theoretical resonant electron-impact vibrational excitation, dissociative recombination and dissociative excitation cross sections of ro-vibrationally excited BeH+ ion

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Theoretical resonant electron-impact vibrational excitation, dissociative recombination and dissociative excitation cross sections of ro-vibrationally excited BeH⁺ ion