Fusion Engineering and design ELSEVIER Fusion Engineering and Design 61-62(2002)307-318 Progress in blanket designs using SiCSic composites L. Giancarli,*, H. Golfier, S. Nishio, R. Raffray, C. Wong, R. Yamada CEA-Saclay, DEN/CPT, 91191 Gif-sur-Yuette, france CEA-Saclay, DENIDMTSERMA, 91191 Gif-sur- Yrette, Fran JAERI, Depa f Fusion Plasma Research, Naka Fusion Research Establishment, 801- Mukouyama, Naka-imachi, Naka-gun Ibaraki-kenn 311-0193, Japan 458 EBU-l1, University of California, San Diego, 9500 Gilman Drice, La Jolla, CA 92093-0417, US.A General Atomics. San Diego, CA 92186-9784. USA This paper summarizes the most recent design activities concerning the use of SicSic composite as structural material for fusion power reactor breeding blanket. Several studies have been performed in the past. The most recent proposals are the tauRo blanket concept in the European Union, the ARIES-AT concept in the US, and DREAM concept in Japan. The first two concepts are self-cooled lithium-lead blankets, while DREAM is an helium-cooled beryllium/ceramic blanket. Both TAURO and aries-at blankets are essentially formed by a sicsic box acting as a container for the lithium-lead which has the simultaneous functions of coolant, tritium breeder, neutron multiplie and, finally, tritium carrier. The dream blanket is characterized by small modules using pebble beds of Be as neutron multiplier material, of Li2O (or other lithium ceramics) as breeder material and of Sic as shielding material. The He coolant path includes a flow through the pebble beds and a porous partition wall. For each blanket, this paper describes the main design features and performances, the most recent design improvements, and the proposed manufacturing routes in order to identify specific issues and requirements for the future R&d on SiCr/Sic c 2002 Published by elsevier Science B V. Keywords: Blanket designs: SiC/SiC composites; Self-cooled lithium-lead 1. Introduction The low activation and afterheat levels asso- ciated with SiC!Sic after long-term neutron The use of SiCdSic composites as structural irradiation allow a design of FPR nuclear compo material for in-vessel components permits to show nents showing high safety standards and simplifie the potential of D-T fusion power reactors(FPR) maintenance schemes. In addition, SicSiC has in terms of safety and environmental impact excellent chemical stability at high temperature, which minimizes mobilization of radioactive pro- Corresponding author. Tel. +33-1-69-08-21-37: fax: +33 Furthermore, the high temperature properties of 6908-58-61 SiCHSic improve energy handling capabilities, E-mail address: luciano. giancarli(@cea fr (L. Giancarli allowing the use of high temperature coolant 0920-3796/02/S- see front c 2002 Published by Elsevier Science B.V. PI:S0920-3796(02)00213-2Progress in blanket designs using SiCf/SiC composites L. Giancarli a,
, H. Golfier b , S. Nishio c , R. Raffray d , C. Wong e , R. Yamada c a CEA-Saclay, DEN/CPT, 91191 Gif-sur-Yvette, France b CEA-Saclay, DEN/DMT/SERMA, 91191 Gif-sur-Yvette, France c JAERI, Department of Fusion Plasma Research, Naka Fusion Research Establishment, 801-1 Mukouyama, Naka-machi, Naka-gun, Ibaraki-kenn 311-0193, Japan d 458 EBU-II, University of California, San Diego, 9500 Gilman Drive, La Jolla, CA 92093-0417, USA e General Atomics, San Diego, CA 92186-9784, USA Abstract This paper summarizes the most recent design activities concerning the use of SiCf/SiC composite as structural material for fusion power reactor breeding blanket. Several studies have been performed in the past. The most recent proposals are the TAURO blanket concept in the European Union, the ARIES-AT concept in the US, and DREAM concept in Japan. The first two concepts are self-cooled lithium/lead blankets, while DREAM is an helium-cooled beryllium/ceramic blanket. Both TAURO and ARIES-AT blankets are essentially formed by a SiCf/SiC box acting as a container for the lithium/lead which has the simultaneous functions of coolant, tritium breeder, neutron multiplier and, finally, tritium carrier. The DREAM blanket is characterized by small modules using pebble beds of Be as neutron multiplier material, of Li2O (or other lithium ceramics) as breeder material and of SiC as shielding material. The He coolant path includes a flow through the pebble beds and a porous partition wall. For each blanket, this paper describes the main design features and performances, the most recent design improvements, and the proposed manufacturing routes in order to identify specific issues and requirements for the future R&D on SiCf/SiC. # 2002 Published by Elsevier Science B.V. Keywords: Blanket designs; SiCf/SiC composites; Self-cooled lithium/lead 1. Introduction The use of SiCf/SiC composites as structural material for in-vessel components permits to show the potential of D/T fusion power reactors (FPR) in terms of safety and environmental impact. The low activation and afterheat levels asso￾ciated with SiCf/SiC after long-term neutron irradiation allow a design of FPR nuclear compo￾nents showing high safety standards and simplified maintenance schemes. In addition, SiCf/SiC has an excellent chemical stability at high temperature, which minimizes mobilization of radioactive pro￾ducts. Furthermore, the high temperature properties of SiCf/SiC improve energy handling capabilities, allowing the use of high temperature coolant
Corresponding author. Tel.: /33-1-69-08-21-37; fax: /33- 1-69-08-58-61 E-mail address: luciano.giancarli@cea.fr (L. Giancarli). Fusion Engineering and Design 61/62 (2002) 307/318 www.elsevier.com/locate/fusengdes 0920-3796/02/$ - see front matter # 2002 Published by Elsevier Science B.V. PII: S 0 9 2 0 - 3 7 9 6 ( 0 2 ) 0 0 2 1 3 - 2