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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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The Chodura sheath for angles of a few degrees between the magnetic field and the surface of divertor targets and limiters

Nuclear fusion, 2012-08, Vol.52 (8), p.83012-10

Stangeby, P.C.

2012

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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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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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Recent DIII-D progress toward validating models of tungsten erosion, re-deposition, and migration for application to next-step fusion devices

Materials research express, 2023-12, Vol.10 (12), p.126503

2023

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A three-dimensional analytic model for discrete limiters in ITER

Nuclear fusion, 2010-03, Vol.50 (3), p.035013-035013

Stangeby, P.C

2010

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Experimental divertor physics

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

1997

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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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Design and physics basis for the upcoming DIII-D SAS-VW campaign to quantify tungsten leakage and transport in a new slot divertor geometry

Physica scripta, 2021-12, Vol.96 (12), p.124073

2021

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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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SOLPS modeling of the effect on plasma detachment of closing the lower divertor in DIII-D

Plasma physics and controlled fusion, 2017-02, Vol.59 (2), p.25009

2017

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The relation between upstream density and temperature widths in the scrape-off layer and the power width in an attached divertor

Nuclear fusion, 2010-12, Vol.50 (12), p.125003

2010

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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

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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

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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

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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

The Chodura sheath for angles of a few degrees between the magnetic field and the surface of divertor targets and limiters

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

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

Recent DIII-D progress toward validating models of tungsten erosion, re-deposition, and migration for application to next-step fusion devices

A three-dimensional analytic model for discrete limiters in ITER

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

Design and physics basis for the upcoming DIII-D SAS-VW campaign to quantify tungsten leakage and transport in a new slot divertor geometry

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

SOLPS modeling of the effect on plasma detachment of closing the lower divertor in DIII-D

The relation between upstream density and temperature widths in the scrape-off layer and the power width in an attached divertor

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

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