Simulation of hydrogen isotope retention in the gap of tungsten divertor tiles
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference25 articles.
1. Plasma-material interactions in current tokamaks and their implications for next step fusion reactors
2. Chapter 4: Power and particle control
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1. Damage and melting of ITER-like flat-type tungsten castellated blocks exposed to long pulse H-mode plasmas;Fusion Engineering and Design;2018-11
2. Energy loss of 100 keV hydrogen isotopes in materials for nuclear applications;International Journal of Hydrogen Energy;2018-05
3. A Particle-In-Cell approach to particle flux shaping with a surface mask;Nuclear Materials and Energy;2017-08
4. Inter-ELM heat loads on tungsten leading edge in the KSTAR divertor;Nuclear Materials and Energy;2017-08
5. Effects of the divertor tile geometries and magnetic field angles on the heat fluxes to the surface;Fusion Engineering and Design;2017-03
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