1 FT/P5-36 IFMIF Target and Test Cell – Towards Design Integration V. Heinzel, D. Leichtle, F. Arbeiter, B. Dolensky, U. Fischer, S. Gordeev, A. Moeslang*, K.- H. Lang, S.P. Simakov, E. Stratmanns, V. Slobodchuk, H. Tsige-Tamirat, P. Vladimirov* Institute for Reactor Safety, Research Centre of Karlsruhe, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany * Institute for Material Research I, Research Centre of Karlsruhe, Hermann-von-Helmholtz- Platz 1, 76344 Eggenstein-Leopoldshafen, Germany Corresponding Author: Volker Heinzel (heinzel@irs.fzk.de) Abstract: The Target and Test Cell of the International-Fusion-Material-Irradiation-Facility (IFMIF) will provide an intense neutron source and qualified irradiation specimen for testing candidate fusion reactor materials. The progress achieved in the design integration of the Target and Test Cell subsystems will be reported with respect to CAD engineering models, the nuclear layout analyses and cooling capabilities by natural convection. A validated set of sophisticated methods, data and tools is now available to continue this ongoing task in the forthcoming EVEDA phase of IFMIF. 1. Introduction The International-Fusion-Material-Irradiation-Facility (IFMIF) is an accelerator driven neutron source for irradiation tests of candidate fusion reactor materials. Two 40 MeV deuterium beams of 125 mA each will hit a flowing liquid lithium jet target, producing high energy neutrons up to 55 MeV at a rate of about 10 17 per second. Those neutrons will penetrate the target back wall made of a thin EUROFER plate. In the attached High Flux Test Module (HFTM), a testing volume of 0.5 litres filled by qualified small scale specimens will be irradiated at displacement rates of 20-50 dpa/fpy in structural materials. The HFTM will also provide helium and hydrogen production to dpa ratios that reflect within the uncertainties the values expected in a DEMO fusion reactor. The Medium Flux Test Module (MFTM) comprises devices for in situ creep-fatigue and tritium release experiments, as well as for tungsten spectral shifter or reflector plates. Further down-stream the low flux region will provide irradiation tubes for additional material irradiation at lower fluence levels. The objective of the present paper is to present the progress achieved in the design integration of the Target and Test Cell of IFMIF. First, work is reported on collecting and harmonizing the CAD designs provided by various international groups involved in the IFMIF Target and Test Cell development. Second, further efforts devoted to the general nuclear layout of the Target and Test Cell are described, taking into account nuclear calculations of responses such as nuclear heating, activation inventories, and dose rates based on most advanced nuclear data and calculational procedures. Finally, results of an extensive study are presented on the cooling capabilities of the Target and Test Cell by natural convection. 2. CAD Design Integration The Target and Test Cell (TTC) is a cavity which contains, among others, the lithium target assembly and the test modules. Several international teams have developed different individual components with the objective to investigate the main functional characteristics and issues of each component separately. The engineering design has been elaborated to fulfil the requirements for that component only and has been neglecting mostly design integration issues.