Scrape-off layer plasmas for ITER with 2nd X-point and convective transport effects
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference15 articles.
1. Overview of goals and performance of ITER and strategy for plasma–wall interaction investigation
2. Scaling laws for edge plasma parameters in ITER from two-dimensional edge modelling
3. Cross-field plasma transport and main-chamber recycling in diverted plasmas on Alcator C-Mod
4. Transport by intermittency in the boundary of the DIII-D tokamak
5. Comparison of particle transport in the scrape-off layer plasmas of Alcator C-Mod and DIII-D
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1. Multiphysics Modeling of Impurity Transport for FNSF Startup Scenario with ERO2.0;Fusion Science and Technology;2023-01-26
2. New proposed ITER divertor design using carbon insert on tungsten to mitigate ELMs and secondary radiation effects on nearby components;Scientific Reports;2022-03-18
3. Prediction of divertor heat flux width for ITER Pre-Fusion Power Operation using BOUT++ transport code;Nuclear Fusion;2021-11-30
4. Potential design problems for ITER fusion device;Scientific Reports;2021-01-22
5. Prediction of divertor heat flux width for ITER using BOUT++ transport and turbulence module;Nuclear Fusion;2019-02-27
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