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Basic physical processes and reduced models for plasma detachment

Plasma physics and controlled fusion, 2018-04, Vol.60 (4), p.44022

Stangeby, P C

2018

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Physics basis and design of the ITER plasma-facing components

Journal of nuclear materials, 2011-08, Vol.415 (1), p.S957-S964

2011

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First Evidence of Local E×B Drift in the Divertor Influencing the Structure and Stability of Confined Plasma near the Edge of Fusion Devices

Physical review letters, 2020-05, Vol.124 (19), p.195002-195002, Article 195002

2020

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Modelling of beryllium erosion–redeposition on ITER first wall panels

Journal of nuclear materials, 2011-08, Vol.415 (1), p.S165-S169

2011

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A full tungsten divertor for ITER: Physics issues and design status

Journal of nuclear materials, 2013-07, Vol.438, p.S48-S56

2013

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Status of the ITER full-tungsten divertor shaping and heat load distribution analysis

Physica scripta, 2014-04, Vol.T159 (1), p.14002

2014

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Experimental divertor physics

Plasma physics and controlled fusion, 1997-06, Vol.39 (6), p.779-930

1997

Volltextzugriff (PDF)

Influence of the E × B drift in high recycling divertors on target asymmetries

Plasma physics and controlled fusion, 2015-07, Vol.57 (9), p.95002

2015

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Reversed-direction 2-point modelling applied to divertor conditions in DIII-D

Plasma physics and controlled fusion, 2024-04, Vol.66 (4), p.45013

2024

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SOL width in limited versus diverted discharges in DIII-D

Journal of nuclear materials, 2011-08, Vol.415 (1), p.S387-S390

2011

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Fluctuation-driven transport in the DIII-D boundary

Plasma physics and controlled fusion, 2002-06, Vol.44 (6), p.717-731, Article 308

2002

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The magnitude of plasma flux to the main-wall in the DIII-D tokamak

Plasma physics and controlled fusion, 2005-10, Vol.47 (10), p.1579-1607

2005

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Developing solid-surface plasma facing components for pilot plants and reactors with replenishable wall claddings and continuous surface conditioning. Part A: concepts and questions

Plasma physics and controlled fusion, 2022-05, Vol.64 (5), p.55018

2022

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3D-DIVIMP(HC) code modeling of DIII-D DiMES porous plug injector experiments

Journal of nuclear materials, 2011-08, Vol.415 (1), p.S145-S148

2011

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Narrow heat flux channels in the COMPASS limiter scrape-off layer

Journal of nuclear materials, 2015-08, Vol.463, p.385-388

2015

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Evaluation of the impact of divertor closure on high-Z material transport and leakage in small angle slot divertor with toroidal tungsten rings in DIII-D

Physica scripta, 2020-03, Vol.T171 (1), p.14072

2020

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A problem in the interpretation of tokamak Langmuir probes when a fast electron component is present

Plasma physics and controlled fusion, 1995-09, Vol.37 (9), p.1031-1037

Stangeby, P C

1995

Volltextzugriff (PDF)

Developing solid-surface plasma facing components for pilot plants and reactors with replenishable wall claddings and continuous surface conditioning. Part B: required research in present tokamaks

Plasma physics and controlled fusion, 2022-05, Vol.64 (5), p.55003

2022

Volltextzugriff (PDF)

Understanding narrow SOL power flux component in COMPASS limiter plasmas by use of Langmuir probes

Journal of nuclear materials, 2015-08, Vol.463, p.381-384

2015

Volltextzugriff (PDF)

Analysis of a tungsten sputtering experiment in DIII-D and code/data validation of high redeposition/reduced erosion

Fusion engineering and design, 2015-05, Vol.94 (C), p.67-71

2015

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First tests of diagnostic mirrors in a tokamak divertor: An overview of experiments in DIII-D

Fusion engineering and design, 2008, Vol.83 (1), p.79-89

2008

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Quantification of chemical erosion in the DIII-D divertor and implications for ITER

Journal of nuclear materials, 2011-08, Vol.415 (1), p.S141-S144

2011

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Parallel flow in the JET scrape-off layer

Plasma physics and controlled fusion, 2000-08, Vol.42 (8), p.905-915

2000

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On the relative roles of neutral transport and plasma transport in the formation of the density pedestal in magnetically confined plasmas

Journal of physics. D, Applied physics, 2003-11, Vol.36 (22), p.2784-2797

Stangeby, P C

2003

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Edge-localized mode dynamics and transport in the scrape-off layer of the DIII-D tokamak

Physics of plasmas, 2005-07, Vol.12 (7)

2005

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Basic physical processes and reduced models for plasma detachment

Physics basis and design of the ITER plasma-facing components

First Evidence of Local E×B Drift in the Divertor Influencing the Structure and Stability of Confined Plasma near the Edge of Fusion Devices

Modelling of beryllium erosion–redeposition on ITER first wall panels

A full tungsten divertor for ITER: Physics issues and design status

Status of the ITER full-tungsten divertor shaping and heat load distribution analysis

Experimental divertor physics

Influence of the E × B drift in high recycling divertors on target asymmetries

Reversed-direction 2-point modelling applied to divertor conditions in DIII-D

SOL width in limited versus diverted discharges in DIII-D

Fluctuation-driven transport in the DIII-D boundary

The magnitude of plasma flux to the main-wall in the DIII-D tokamak

Developing solid-surface plasma facing components for pilot plants and reactors with replenishable wall claddings and continuous surface conditioning. Part A: concepts and questions

3D-DIVIMP(HC) code modeling of DIII-D DiMES porous plug injector experiments

Narrow heat flux channels in the COMPASS limiter scrape-off layer

Evaluation of the impact of divertor closure on high-Z material transport and leakage in small angle slot divertor with toroidal tungsten rings in DIII-D

A problem in the interpretation of tokamak Langmuir probes when a fast electron component is present

Developing solid-surface plasma facing components for pilot plants and reactors with replenishable wall claddings and continuous surface conditioning. Part B: required research in present tokamaks

Understanding narrow SOL power flux component in COMPASS limiter plasmas by use of Langmuir probes

Analysis of a tungsten sputtering experiment in DIII-D and code/data validation of high redeposition/reduced erosion

First tests of diagnostic mirrors in a tokamak divertor: An overview of experiments in DIII-D

Quantification of chemical erosion in the DIII-D divertor and implications for ITER

Parallel flow in the JET scrape-off layer

On the relative roles of neutral transport and plasma transport in the formation of the density pedestal in magnetically confined plasmas

Edge-localized mode dynamics and transport in the scrape-off layer of the DIII-D tokamak

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