Volker Heinzel

TL;DR: A modular He-cooled divertor concept with integrated pin array (HEMP) is being developed at the Forschungszentrum Karlsruhe to achieve a high heat flux of at least about 10–15 MW/m 2, proposed for a near-term reactor model like DEMO.

TL;DR: The High Flux Test Module (HFTM) as mentioned in this paper was developed with the objective to facilitate the controlled irradiation of steel samples in the high flux area directly behind the International Fusion Materials Irradiation Facility (IFMIF) neutron source.

TL;DR: In this article, a modified version of the NJOY code was used to estimate the number of primary survived and clustered defects in the α-iron irradiated in the high flux test module of IFMIF.

TL;DR: In this paper, a detailed geometrical model for Monte Carlo neutronic calculations has been prepared directly from engineering CAD data by utilizing the McCad conversion software developed at KIT, which includes detailed descriptions of the lithium target system proposed by Japan, all test modules based on the EVEDA phase design, and the 3dimesional arrangement of the biological shielding.

TL;DR: In this paper, the authors describe the latest design of liquid lithium (Li) target system in International Fusion Materials Irradiation Facility (IFMIF), which is an accelerator-driven intense neutron source for fusion reactor materials testing.