Beryllium and graphite performance in ITER during a disruption

Hassanein, A.; Ehst, D.A.; Gahl, J.M.

doi:10.1016/0022-3115(94)91034-0

Cited by 17 publications

(7 citation statements)

References 11 publications

(2 reference statements)

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Other work has focused separately on issues such as radiation transport [8], simulation experiments [9], and magnetic field effects [10].…”

Section: Introductionmentioning

confidence: 99%

“…The volumetric energy deposition function Cl(y,t) is calculated, in the condensed target material, with detailed models that include the slowing-down physics of plasma particles (both ions and electrons) in various target materials [9]. Phase change of metallic materials, when temperature exceeds their melting points are calculated using previously developed models [12,13].…”

mentioning

confidence: 99%

See 1 more Smart Citation

Comprehensive model for disruption erosion in a reactor environment

Hassanein

Konkashbaev

1995

Journal of Nuclear Materials

Self Cite

View full text Add to dashboard Cite

A comprehensive disruption erosion model which takes into account the interplay of major physical processes during plasma-material interaction has been developed. The model integrates with sufficient detail and in a self-consistent way, material thermal evolution response, plasma-vapor interaction physics, vapor hydrodynamics and radiation transport in order to realistically simulate the effects of a plasma disruption on plasma-facing components. Candidate materials such as beryllium and carbon have been analyzed. The dependence of the net erosion rate on disruption physics and various parameters was analyzed and is discussed.

show abstract

“…Other work has focused separately on issues such as radiation transport [8], simulation experiments [9], and magnetic field effects [10].…”

Section: Introductionmentioning

confidence: 99%

mentioning

confidence: 99%

Comprehensive model for disruption erosion in a reactor environment

Hassanein

Konkashbaev

1995

Journal of Nuclear Materials

Self Cite

View full text Add to dashboard Cite

show abstract

“…The boundary condition at the surface can then be given by where qgas is the net heat flux from i, ,e near-wall vapor zone; qrad is the radiation heat flux absorbed at the material surface; and qevap is the evaporated heat flux, as determined by the enthalpy of evaporation. The volumetric energy deposition function q (Z,t) is calculated, in the condensed target material, with detailed models that include the slowing-down physics of plasma particles (both ions and electrons) in various target materials [9]. Phase change of metallic materials, when temperature exceeds their melting points are calculated using previously developed models [ 131.…”

Section: Materials Thermal Evolutionmentioning

confidence: 99%

“…Other work has focused separately on issues such as radiation transport [8], simulation experiments [9], and magnetic field effects [lo].…”

Section: Introductionmentioning

confidence: 99%

Modeling plasma/material interactions during a tokamak disruption

Hassanein¹,

Konkashbaev²

1994

Self Cite

View full text Add to dashboard Cite

show abstract

“…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. Echols and Winfrey conducted computational work using the electrothermal plasma code ETFLOW in the ideal plasma regime for capillary discharge to simulate high heat flux deposition on materials and their ablative behavior [5] .…”

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.

View full text Add to dashboard Cite

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.

show abstract

Beryllium and graphite performance in ITER during a disruption

Cited by 17 publications

References 11 publications

Comprehensive model for disruption erosion in a reactor environment

Comprehensive model for disruption erosion in a reactor environment

Modeling plasma/material interactions during a tokamak disruption

Computational Investigation of Beryllium and Lithium Performance in Future Fusion Tokamaks

Contact Info

Product

Resources

About