eprintid: 12491 rev_number: 27 eprint_status: archive userid: 1903 dir: disk0/00/01/24/91 datestamp: 2012-08-08 10:52:34 lastmod: 2023-03-03 09:27:50 status_changed: 2023-03-03 09:27:50 type: conference_item metadata_visibility: show item_issues_count: 0 creators_name: Gonzalez, M. creators_name: Carella, E. creators_name: Hernandez, T. creators_name: Jimenez Rey, D. creators_name: Gonzalez Arrabal, Raquel title: Ion Beam Analysis of He-implanted fusion solid breedes ispublished: pub subjects: nuclear subjects: fisica abstract: Introduction Lithium-based ceramics (silicates, titanates, ?) possess a series of advantages as alternative over liquid lithium and lithium-lead alloys for fusion breeders. They have a sufficient lithium atomic density (up to 540 kg*m-3), high temperature stability (up to 1300 K), and good chemical compatibility with structural materials. Nevertheless, few research is made on the diffusion behavior of He and H isotopes through polycrystalline structures of porous ceramics which is crucial in order to understand the mobility of gas coolants as well as, the release of tritium. Moreover, in the operating conditions of actual breeder blanket concepts, the extraction rate of the helium produced during lithium transmutation can be affected by the composition and the structure of the near surface region modifying the performance of BB materials date: 2011 date_type: published official_url: http://www.ornl.gov/icfrm15/ full_text_status: public pres_type: poster event_title: 15th International Conference on Fusion Reactor Materials event_location: Charleston, EE. UU event_dates: 16/10/2011 - 22/10/2011 event_type: conference institution: Industriales department: Ingenieria_Nuclear refereed: TRUE book_title: Proceedings of 15th International Conference on Fusion Reactor Materials rights: by-nc-nd citation: Gonzalez, M. and Carella, E. and Hernandez, T. and Jimenez Rey, D. and Gonzalez Arrabal, Raquel (2011). Ion Beam Analysis of He-implanted fusion solid breedes. In: "15th International Conference on Fusion Reactor Materials", 16/10/2011 - 22/10/2011, Charleston, EE. UU. document_url: https://oa.upm.es/12491/1/INVE_MEM_2011_105324.pdf