Browsing by Author MATERA Roberto

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Publication YearJRC N°TitleAuthor(s), Editor(s), Other Contributor(s)Publication Type
1991JRC6833Behaviour of First Wall Components under Thermal FatigueRENDA Vito; MATERA Roberto; BIGGIO Michele; ETO M.; CICCHETTI ErmoloContributions to Conferences
1994JRC10187Critical Assessment of First Wall Behaviour under Cyclic Heat LoadsMATERA Roberto; MEROLA Mario; VIEIDER G.; BOUVERET Y.; LAKESTANI FereydounArticles in Journals
1992JRC8847Critical Issues and Innovative Solutions for the Divertor Plate Design in Future Experimental Tokamak-Type Fusion ReactorsMATERA Roberto; DE MEESTER P.Contributions to Conferences
1991JRC6834Design Optimization Study of an Innovative Concept of Divertor Plate Based on Fibre Composite TechnologyMATERA Roberto; JANSSENS Willem; DE MEESTER P.Contributions to Conferences
1991JRC7920Design Problems of the NET/ITER Experimental Reactor First WallMATERA Roberto; MEROLA MarioArticles in Journals
1989JRC6115Evaluation of Creep Damage in an Mn-Cr Stainless SteelMATERA RobertoArticles in Journals
1995JRC12197Experimental Results of the Thermal Fatigue Tests for IAEA Benchmark ComponentsMEROLA Mario; MATERA Roberto; SEVINI FilippoContributions to Conferences
1988JRC5244High Temperature Time Dependent Allowable Stress and Isochronous Curves of an Austenitic Mn-Cr SteelMATERA RobertoContributions to Conferences
1992JRC8848High Thermal Performance CFC DivertorMATERA Roberto; MEROLA MarioContributions to Conferences
1991JRC8008High Thermal Performance Divertor PlateMATERA Roberto; MEROLA MarioEUR - Scientific and Technical Research Reports
2000JRC18589Irradiation Creep Induced Stress Relaxation of Inconel 718.SCHOLZ Reinhard; MATERA RobertoContributions to Conferences
1991JRC8045ITER First Wall and Divertor Design and its Influence on Materials Selection (Including First Wall Test Results)MATERA Roberto; VIEIDER G.; AKIBA M.; WATSON B.Contributions to Conferences
1987JRC4840Materials for Fusion ReactorsMATERA RobertoArticles in Journals
1988JRC5262Microstructural Evolution in Long Duration Creep Specimens of a Mn-Cr Austenitic SteelRUEDL Erich; MATERA RobertoArticles in Journals
1999JRC18631Novel Designs of the ITER Gas Box °Liner Aimed at Reducing Tritium Codeposition.CAZZOLA C.; BOSCARY J.; MATERA RobertoContributions to Conferences
1990JRC7629Optimization Design Study of an Innovative Divertor Concept for Future Experimental Tokamak-Type Fusion ReactorsMATERA RobertoEUR - Scientific and Technical Research Reports
1989JRC5832Oxidation of a Mn-Cr Austenitic Steel during Creep Testing and its Interaction with the FractureRUEDL Erich; MATERA RobertoArticles in Journals
1991JRC8040Preliminary Theoretical and Experimental Study of the Effects of Plasma Disruptions on the Thermal Fatigue Lifetime of the ITER/NET First WallMATERA Roberto; MEROLA MarioContributions to Conferences
2000JRC18598Proton Irradiation Creep of Inconel 718 at 300°CSCHOLZ Reinhard; MATERA RobertoContributions to Conferences
1991JRC7996Residual Strain in Fusion Reactor First Wall Component Subjected to Thermal FatigueMATERA Roberto; MEROLA Mario; RUSTICHELLI F.; PERRIN M.Articles in Journals