5-9 September 2016
Prague Congress Centre
Europe/Prague timezone

P4.179 Mechanical testing of the IFMIF HFTM-DC prototype during operation in the HELOKA-LP helium loop

8 Sep 2016, 14:20
1h 40m
Foyer 2A (2nd floor), 3A (3rd floor) (Prague Congress Centre)

Foyer 2A (2nd floor), 3A (3rd floor)

Prague Congress Centre

5. května 65, Prague, Czech Republic
Board: 179
Poster I. Materials Technology P4 Poster session

Speaker

Georg Schlindwein (Institute for Neutron Physics and Reactor Technology (INR))

Description

The so called High Flux Test Module (HFTM) represents the component of IFMIF (International Fusion Irradiation Facility) in which material specimens are being placed that accumulate the highest neutron induced damage rates (≥20 dpa/fpy). Damage rates of this magnitude are limited to a volume of ~500 cm³ (attenuation in beam direction) behind a beam footprint of 20x5 cm. The high flux region of the module is contained in a flat faced, cuboid volume of 5.6 cm depth. Efforts for a high spatial utilization and the demand for a high neutron transmission require a thin-walled container design. An array of mini-channels (1 mm gap) through which low pressure (0.3 MPa) helium gas flows was chosen as an efficient, space-saving method to cool the container and the material specimens. Due to place constraints between the target and the other irradiation modules the HFTM is implemented as a slender and long construction with features that are challenging for pressurized equipment. Experimental studies on a 1:1 prototype of the HFTM-DC (double compartment) were conducted in the Helium Loop Karlsruhe – Low Pressure (HELOKA-LP) during 2015. The experiments also included intensive testing to demonstrate the mechanical reliability of the HFTM under IFMIF relevant operation conditions. Therefore, the module is instrumented with numerous sensors which measure displacement, deformation and mechanical strain. The reactions on temperature and pressure loads were studied. In this paper the experimental results will be presented and compared to the numerical (FEM) simulation studies.

Co-authors

Bernhard Dolensky (Institute for Neutron Physics and Reactor Technology (INR), Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen, Germany) Christine Klein (Institute for Neutron Physics and Reactor Technology (INR), Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen, Germany) Florian Schwab (Institute for Neutron Physics and Reactor Technology (INR), Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen, Germany) Frederik Arbeiter (Institute for Neutron Physics and Reactor Technology (INR), Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen, Germany) Georg Schlindwein (Institute for Neutron Physics and Reactor Technology (INR), Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen, Germany) Kevin Zinn (Institute for Neutron Physics and Reactor Technology (INR), Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen, Germany)

Presentation Materials

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