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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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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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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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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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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

Stangeby, P.C.

2012

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Hyperhaploidy is a novel high-risk cytogenetic subgroup in multiple myeloma

Leukemia, 2017-03, Vol.31 (3), p.637-644

2017

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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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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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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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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 three-dimensional analytic model for discrete limiters in ITER

Nuclear fusion, 2010-03, Vol.50 (3), p.35013

Stangeby, P.C.

2010

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High gas throughput SOLPS-ITER simulations extending the ITER database to strong detachment

Nuclear fusion, 2022-10, Vol.62 (10), p.106017

2022

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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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Thermal management of tungsten leading edges in DIII-D

Fusion engineering and design, 2017-11, Vol.124, p.271-275

2017

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Accounting for Debye sheath expansion for proud Langmuir probes in magnetic confinement fusion plasmas

Review of scientific instruments, 2018-01, Vol.89 (1)

2018

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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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The inter-ELM tungsten erosion profile in DIII-D H-mode discharges and benchmarking with ERO+OEDGE modeling

Nuclear fusion, 2017-04, Vol.57 (5), p.56034

2017

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Controlling marginally detached divertor plasmas

Nuclear fusion, 2017-05, Vol.57 (6), p.66039

2017

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Measurements of multiple heat flux components at the divertor target by using surface eroding thermocouples (invited)

Review of scientific instruments, 2022-10, Vol.93 (10)

2022

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Impact of ELM control techniques on tungsten sputtering in the DIII-D divertor and extrapolations to ITER

Physics of plasmas, 2019-06, Vol.26 (6)

2019

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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 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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Basic physical processes and reduced models for plasma detachment

Physics basis and design of the ITER plasma-facing components

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

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

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

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

Hyperhaploidy is a novel high-risk cytogenetic subgroup in multiple myeloma

Modelling of beryllium erosion–redeposition on ITER first wall panels

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

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

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

A three-dimensional analytic model for discrete limiters in ITER

High gas throughput SOLPS-ITER simulations extending the ITER database to strong detachment

Experimental divertor physics

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

Thermal management of tungsten leading edges in DIII-D

Accounting for Debye sheath expansion for proud Langmuir probes in magnetic confinement fusion plasmas

SOL width in limited versus diverted discharges in DIII-D

The inter-ELM tungsten erosion profile in DIII-D H-mode discharges and benchmarking with ERO+OEDGE modeling

Controlling marginally detached divertor plasmas

Measurements of multiple heat flux components at the divertor target by using surface eroding thermocouples (invited)

Impact of ELM control techniques on tungsten sputtering in the DIII-D divertor and extrapolations to ITER

Fluctuation-driven transport in the DIII-D boundary

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

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