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CD-III - Parametric Neutronic Analysis of HCLL Blanket for DEMO
J. Jordanova 1), U. Fischer 2), P. Pereslavtsev 2), Y. Poitevin 3), A. Li Puma 3), N. Nikolova-Todorova 4)
1) Institute for Nuclear Research and Nuclear Energy, 1784 Sofia, Bulgaria
2) Forschungszentrum Karlsruhe, Postfach 3640, 76021 Karlsruhe, Germany
3) CEA Saclay, DEN/DM2S/SERMA/LCA, 91191 Gif-sur-Yvette, France
4) University of Shumen “Ep.Konst. Preslavski”, 9700 Shumen, Bulgaria
Abstract: Three-dimensional parametric neutronics calculations using the Monte Carlo code MCNP-4C have been performed for the DEMO-type reactor based on the Helium-Cooled Lithium-Lead blanket. The aim of the analysis is to reduce the radial length of the blanket as much as possible to a level ensuring tritium self-sufficiency and to assess shielding performance of the reactor. It was found that assuming 90% 6Li enrichment, the reference blanket and that with reduced breeder zone length to 55 cm achieve TBR ensuring tritium self-sufficiency, while blanket with 60% 6Li enrichment requires breeder zone length of 75 cm to cover the requited margin. Taking into account the radiation load to the super-conducting toroidal-field coil it was found that the blanket with reduced radial length to 55 cm utilizing either WC-composite as a shield and vacuum vessel of cryogenic steel or two-component shield of Eurofer and WC and vacuum vessel ITER-FDR design demonstrates the best shielding performance in terms of radiation load below the design limit.
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Synopsis (pdf)