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Blanket Shield and Neutronic

Further Adaptation of the European Ceramic-B.I.T. Blanket Conceptual Design to Updated DEMO Specifications

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Pages 2152-2158 | Published online: 10 Aug 2017

References

  • E. PROUST, L. ANZIDEI et al., “Status of the design and feasibility assessment of the European Helium-Cooled Ceramic B.I. T. Test Blanket,” Proceedings of the 9th Topical Meeting on the Technology of Fusion Energy, Oak Brook (IL), October 1990, Fusion Technology, 19, N°3, Part 2A, p. 944.
  • L. ANZIDEI et al., “Design of a Poloidal B.I. T. Blanket for a DEMO Plant,” Proceedings of the 16th Symposium on Fusion Technology, London (UK), September 1990, Part A, p. 964.
  • E. PROUST et al., “Feasibility and Performance Assessment of a Helium-Cooled DEMO Blanket with Poloidal Cooling and Ceramic Breeder inside tubes,” Proceedings of the 16th Symposium on Fusion Technology, London (UK), September 1990, Part A, p. 988.
  • L. GIANCARLI, L. PETRIZZI et al., “Three-Dimensional Neutronic Analy-sis of the European Ceramic B.I. T. DEMO Blanket,” Proceedings of 2nd International Symposium Fusion Nuclear Technology, Karlsruhe (FRG), June 1991, Part B, p. 145–151.
  • A. BAUR, “Programme de Monte Carlo Polycinétique à trois dimensions TRIPOLI-01,” CEA Internal Report (1971).
  • B. BIELAK et al., “Outlines of a Development Proposal for the NET Shielding Blanket Assembly,” 2nd International Symposium on Fusion Nuclear Technology, June 2-7, 1991, Karlsruhe (FRG), Part A, p. 401.
  • L. ANZIDEI, E. PROUST et al., “First Adaptation of the European Ceramics B.I. T. blanket design to the updated DEMO specifications,” in Proc. 2nd International Symposium on Fusion Nuclear Technology, June 2-7, 1991, Karlsruhe (FRG), Part A, p. 117–122.

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