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Thermonuclear fusion has the potential of large-scale sustainable energy production. ITER is a scientific research machine which is currently being built in order to demonstrate that fusion is a feasible energy source. An important component of ITER is the divertor, or ‘exhaust’, which extracts impurities and helium from plasma. Recently, it has been decided that ITER will operate with a full tungsten divertor from the start. Rianne ’t Hoen seeks to predict tritium retention in neutron damaged tungsten under high-flux plasma exposure. Her chief aim is to investigate deuterium retention in pre-irradiation damaged tungsten under high-flux plasma bombardment.

Event details of Deuterium retention in radiation damaged tungsten
Date 6 May 2014
Time 14:00 -15:00
Location Agnietenkapel

M.H.J. 't Hoen, Deuterium Retention in Radiation Damaged Tungsten Exposed to High-Flux Plasma.


Prof. A.W. Kleijn


Dr P.A. Zeijlmans van Emmichoven (UU)


Oudezijds Voorburgwal 229 - 231
1012 EZ Amsterdam


This event is open to the public.