Development of the water cooled lithium lead blanket for DEMO |
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| Affiliation: | 1. CEA-Saclay, DEN/DANS/DM2S/SEMT/BCCR, 91191 Gif Sur Yvette Cedex, France;2. CEA-Saclay, DEN/DANS/DM2S/SERMA/LPEC, 91191 Gif Sur Yvette Cedex, France;1. Korea Atomic Energy Research Institute, Daejeon, Republic of Korea;2. National Fusion Research Institute, Daejeon, Republic of Korea;1. Institute of Advanced Energy, Kyoto University, Gokasho, Uji, Kyoto 611-0011, Japan;2. Graduate School of Science and Technology, Kumamoto University, 2-39-1 Kurokami, Kumamoto 860-8555, Japan;3. Institute of Pulsed Power Science, Kumamoto University, 2-39-1 Kurokami, Kumamoto 860-8555, Japan;1. Open Joint-Stock Company “N.A. Dollezhall Research and Development Institute of Power Engineering,” (OJSC “NIKIET”), 107140, Malaya Krasnoselskaya 2/8, Moscow, Russian Federation;2. D.V. Efremov Scientific Research Institute of Electrophysical Apparatus, 196641 St. Petersburg, Russian Federation;1. University of Pisa, Dipartimento di Ingegneria Civile e Industriale, Largo Lucio Lazzarino 2, 56122 Pisa, Italy;2. ENEA Brasimone, 40032 Camugnano, Bologna, Italy;1. Dipartimento di Energia, Ingegneria dell’Informazione e Modelli Matematici, Università di Palermo, Viale delle Scienze, I-90128 Palermo, Italy;2. ENEA C.R. Brasimone, I-40032 Camugnano, BO, Italy |
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| Abstract: | The water cooled lithium lead (WCLL) blanket, based on near-future technology requiring small extrapolation from present-day knowledge both on physical and technological aspect, is one of the breeding blanket concepts considered as possible candidates for the EU DEMOnstration power plant.In 2012, the EFDA agency issued new specifications for DEMO: this paper describes the work performed to adapt the WCLL blanket design to those specifications.Relatively small modules with straight surfaces are attached to a common Back Supporting Structure housing feeding pipes. Each module features reduced activation ferritic-martensitic steel as structural material, liquid Lithium-Lead as breeder, neutron multiplier and carrier. Water at typical Pressurized Water Reactors (PWR) conditions is chosen as coolant.A preliminary design of the equatorial outboard module has been achieved. Finite elements analyses have been carried out in order to assess the module thermal behavior. Two First Wall (FW) concepts have been proposed, one favoring the thermal efficiency, the other favoring the manufacturability. The Breeding Zone has been designed with C-shaped Double-Walled Tubes in order to minimize the Water/Pb-15.7Li interaction likelihood.The priorities for further development of the WCLL blanket concept are identified in the paper. |
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| Keywords: | DEMO Blanket WCLL Design |
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