Theoretical Calculation of Effective Ionic Charge with Lithium Limiter on HT-7 Tokamak

Asif, M.

doi:10.1007/s10894-014-9676-7

Cited by 3 publications

(1 citation statement)

References 22 publications

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“…Lithium has strong oxygen getter activity and strong hydrogen retention [2] . Beryllium has the advantage of being a low-Z material so low risk of plasma contamination, non-reactive with hydrogenic isotopes and has good thermal conductivity [3,4] , however, its dust is toxic when ablating and expanding into the vacuum vessel of the reactor.…”

Section: Introductionmentioning

confidence: 99%

Computational Investigation of Beryllium and Lithium Performance in Future Fusion Tokamaks

Elbasha

Bourham

Mohamed

2022

new n.a. exploit. and appl.

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Low-z materials are exemplary candidates in tiling critical plasma-facing components in future fusion reactors due to their low ablation rates under intense high heat fluxes especially during abnormal and hard disruption events. Beryllium and Lithium as low-z materials show good performance as plasma-facing materials in current tokamak. Future tokamaks will exhibit long duration hard disruptions, which in turn requires further investigation of plasma-facing materials, as Li and Be, to judge their performance and evaluate their erosion rates. Electrothermal plasma capillary discharges are used to simulate the high-heat flux deposition on materials to assess their erosion rates. The electrothermal plasma code ETFLOW, which is written for capillary discharges to predict the plasma parameters and erosion rates is used to simulate the high-heat flux conditions similar to expected disruption events for simulated heat fluxes from as low as ~50 to as high as ~290 GW/m2 with a reconnoitering of generating the Be and Li plasmas up to the third ionization (Br+++, Li+++). Performance of Be and Li under the lowest capillary discharge currents (50 kA and 100 kA) is almost identical, however, Li shows sharper increase in the plasma pressure, heat flux, total ablated mass and the exit velocities than Be for higher discharge currents (150, 200 and 250 kA). This huge difference between the performance of Li and Be under low and high heat fluxes can be an important issue for the future magnetic fusion reactors.

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Section: Introductionmentioning

confidence: 99%

Computational Investigation of Beryllium and Lithium Performance in Future Fusion Tokamaks

Elbasha

Bourham

Mohamed

2022

new n.a. exploit. and appl.

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Study of the corrosion characteristics of 304 and 316L stainless steel in the static liquid lithium

Zhang

Meng

Zuo

et al. 2021

Journal of Nuclear Materials

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Theoretical calculation of electron density and temperature in the edge of tokamak

Asif

2017

Mod. Phys. Lett. B

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In this work, we use a method based on the concept of particle confinement time [Formula: see text] uniqueness to calculate the electron density and temperature in ohmically heated, edge plasma of the Hefei tokamak-7. Here, with the help of the data taken from Johnson and Hinnov’s table, we have done an extensive work to find electron densities and temperatures that satisfy the [Formula: see text] uniqueness to evaluate the temporal evolution of electron density [Formula: see text] and temperature [Formula: see text]. The results are in good agreement as measured from the Langmuir probe array in previous works.

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Theoretical Calculation of Effective Ionic Charge with Lithium Limiter on HT-7 Tokamak

Cited by 3 publications

References 22 publications

Computational Investigation of Beryllium and Lithium Performance in Future Fusion Tokamaks

Computational Investigation of Beryllium and Lithium Performance in Future Fusion Tokamaks

Study of the corrosion characteristics of 304 and 316L stainless steel in the static liquid lithium

Theoretical calculation of electron density and temperature in the edge of tokamak

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