COMPARATIVE ASSESSMENT OF MATERIAL PERFORMANCE IN DEMO FUSION REACTORS

COMPARATIVE ASSESSMENT OF MATERIAL PERFORMANCE IN DEMO FUSION REACTORS

COMPARATIVE ASSESSMENT OF MATERIAL PERFORMANCE IN DEMO FUSION REACTORS 150 150 UKAEA Opendata

COMPARATIVE ASSESSMENT OF MATERIAL PERFORMANCE IN DEMO FUSION REACTORS

A key goal for fusion materials modelling research is the development of predictive simulation models and capabilities to assess material performance under the neutron irradiation conditions expected in near-plasma regions of fusion reactor tokamaks. This paper presents computational results from the modelling of neutron fields in the latest concepts for the next-step demonstration fusion reactor, DEMO. In particular, the variation in neutron exposure as a function of coolant choice and tritium-breeding blanket concept are described, and the calculated neutron spectra are then applied to predict damage rates, helium production rates, and helium-induced grain-boundary embrittlement lifetimes—updating previous estimates derived using an earlier DEMO model.

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24/03/2014