UB Paderborn / Katalog / Suche / in CDI

Sortiert nach

Einfacher Volltextzugriff von (fast) überall

Installieren Sie die LibKey Nomad-Browsererweiterung und erhalten Sie von vielen Webseiten einfachen Zugriff auf lizenzierte Volltexte oder Open Access Publikationen. Mehr erfahren...

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

Volltextzugriff (PDF)

Physics basis and design of the ITER plasma-facing components

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

2011

Volltextzugriff (PDF)

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

Volltextzugriff (PDF)

Modelling of beryllium erosion–redeposition on ITER first wall panels

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

2011

Volltextzugriff (PDF)

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

Volltextzugriff (PDF)

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

Volltextzugriff (PDF)

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

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

2013

Volltextzugriff (PDF)

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

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

2014

Volltextzugriff (PDF)

A three-dimensional analytic model for discrete limiters in ITER

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

Stangeby, P.C.

2010

Volltextzugriff (PDF)

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

Volltextzugriff (PDF)

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

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

2018

Volltextzugriff (PDF)

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

Volltextzugriff (PDF)

SOL width in limited versus diverted discharges in DIII-D

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

2011

Volltextzugriff (PDF)

Fluctuation-driven transport in the DIII-D boundary

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

2002

Volltextzugriff (PDF)

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

Volltextzugriff (PDF)

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

Volltextzugriff (PDF)

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

Volltextzugriff (PDF)

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

Volltextzugriff (PDF)

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

Volltextzugriff (PDF)

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

Volltextzugriff (PDF)

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

Volltextzugriff (PDF)

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

Volltextzugriff (PDF)

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

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

2015

Volltextzugriff (PDF)

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

Volltextzugriff (PDF)

1 – 25 von 452

Suche als RSS-Feed

Suchergebnisse filtern

Filter anzeigen

Nur zeigen

Geprüft (Peer-Review)
(431)
Mit Volltextzugriff
(360)

Publikationsform

Artikel
(394)
Tagungsberichte
(58)

Sprache

Englisch
(449)
Russisch
(1)

Erscheinungsjahr

n.n

Menü

Weitere Dienste

Einstellungen

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

Suchergebnisse filtern