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Wall conditioning on ITER

Journal of nuclear materials, 2011-08, Vol.415 (1), p.S1013-S1016

2011

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SOLPS-ITER Modeling of the Alcator C-Mod Divertor Plasma

Plasma and Fusion Research, 2016/08/19, Vol.11, pp.1403103-1403103

2016

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SOLEDGE3X full vessel plasma simulations for computation of ITER first‐wall fluxes

Contributions to plasma physics (1988), 2022-06, Vol.62 (5-6), p.n/a

2022

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Assessing global beryllium erosion via tomographic reconstruction of 3D beryllium emission profiles in ITER

Plasma physics and controlled fusion, 2024-02, Vol.66 (2), p.25010

2024

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First Monte‐Carlo modelling of global beryllium migration in ITER using ERO2.0

Contributions to plasma physics (1988), 2020-06, Vol.60 (5-6), p.n/a

2020

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SOLPS-ITER drift modelling of JET Ne and N-seeded H-modes

Nuclear materials and energy, 2021-09, Vol.28, p.101030, Article 101030

2021

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SOLPS-ITER drift modelling of ITER burning plasmas with narrow near-SOL heat flux channels

Nuclear materials and energy, 2021-03, Vol.26, p.100870, Article 100870

2021

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Implementation of a 9-point stencil in SOLPS-ITER and implications for Alcator C-Mod divertor plasma simulations

Nuclear materials and energy, 2019-01, Vol.18, p.125-130

2019

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Impact of enhanced far-SOL transport on first wall fluxes in ITER from full vessel edge-plasma simulations

Nuclear materials and energy, 2022-10, Vol.33, p.101293, Article 101293

2022

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Overview of plasma–material interaction experiments on EAST employing MAPES

Journal of nuclear materials, 2014-12, Vol.455 (1-3), p.710-716

2014

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Comparing N versus Ne as divertor radiators in ASDEX-upgrade and ITER

Nuclear materials and energy, 2019-05, Vol.19, p.72-78

2019

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The WEST programme: Minimizing technology and operational risks of a full actively cooled tungsten divertor on ITER

Fusion engineering and design, 2013-10, Vol.88 (6-8), p.497-500

2013

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Inter-ELM heat loads on tungsten leading edge in the KSTAR divertor

Nuclear materials and energy, 2017-08, Vol.12, p.1122-1129

2017

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Impact of gas injection location and divertor surface material on ITER fusion power operation phase divertor performance assessed with SOLPS-ITER

Nuclear fusion, 2024-03, Vol.64 (3), p.36002

2024

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Improved scaling law for the prediction of deuterium retention in beryllium co-deposits

Nuclear fusion, 2022-03, Vol.62 (3), p.36006

2022

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Resolidification-controlled melt dynamics under fast transient tokamak plasma loads

Nuclear fusion, 2020-10, Vol.60 (10), p.104001

2020

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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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Role of turbulent separatrix tangle in the improvement of the integrated pedestal and heat exhaust issue for stationary-operation tokamak fusion reactors

Nuclear fusion, 2024-05, Vol.64 (5), p.56041

2024

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Predictive modeling of the JET D–T plasma boundary

Contributions to plasma physics (1988), 2023-12

2023

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Feasibility of raised inner strike point equilibria scenario in ITER for detritiation from beryllium co-deposits

Nuclear fusion, 2023-07, Vol.63 (7), p.76027

2023

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Heuristic predictions of RMP configurations for ELM suppression in ITER burning plasmas and their impact on divertor performance

Nuclear fusion, 2024-07, Vol.64 (7), p.76035

2024

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Evaluation of ITER divertor shunts as a synthetic diagnostic for detachment control

Nuclear fusion, 2023-08, Vol.63 (8), p.86002

2023

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Measurements and modeling of type-I and type-II ELMs heat flux to the DIII-D divertor

Nuclear fusion, 2023-08, Vol.63 (8), p.86031

2023

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Validation of the ERO2.0 code using W7-X and JET experiments and predictions for ITER operation

Nuclear fusion, 2024-08, Vol.64 (8), p.86016

2024

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Wall conditioning on ITER

SOLPS-ITER Modeling of the Alcator C-Mod Divertor Plasma

SOLEDGE3X full vessel plasma simulations for computation of ITER first‐wall fluxes

Assessing global beryllium erosion via tomographic reconstruction of 3D beryllium emission profiles in ITER

First Monte‐Carlo modelling of global beryllium migration in ITER using ERO2.0

SOLPS-ITER drift modelling of JET Ne and N-seeded H-modes

SOLPS-ITER drift modelling of ITER burning plasmas with narrow near-SOL heat flux channels

Implementation of a 9-point stencil in SOLPS-ITER and implications for Alcator C-Mod divertor plasma simulations

Impact of enhanced far-SOL transport on first wall fluxes in ITER from full vessel edge-plasma simulations

Overview of plasma–material interaction experiments on EAST employing MAPES

Comparing N versus Ne as divertor radiators in ASDEX-upgrade and ITER

The WEST programme: Minimizing technology and operational risks of a full actively cooled tungsten divertor on ITER

Inter-ELM heat loads on tungsten leading edge in the KSTAR divertor

Impact of gas injection location and divertor surface material on ITER fusion power operation phase divertor performance assessed with SOLPS-ITER

Improved scaling law for the prediction of deuterium retention in beryllium co-deposits

Resolidification-controlled melt dynamics under fast transient tokamak plasma loads

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

Role of turbulent separatrix tangle in the improvement of the integrated pedestal and heat exhaust issue for stationary-operation tokamak fusion reactors

Predictive modeling of the JET D–T plasma boundary

Feasibility of raised inner strike point equilibria scenario in ITER for detritiation from beryllium co-deposits

Heuristic predictions of RMP configurations for ELM suppression in ITER burning plasmas and their impact on divertor performance

Evaluation of ITER divertor shunts as a synthetic diagnostic for detachment control

Measurements and modeling of type-I and type-II ELMs heat flux to the DIII-D divertor

Validation of the ERO2.0 code using W7-X and JET experiments and predictions for ITER operation

Helium plasma operations on ASDEX Upgrade and JET in support of the non-nuclear phases of ITER

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