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The test blanket modules project in Europe : From the strategy to the technical plan over next 10 yearsPOITEVIN, Y; BOCCACCINI, L. V; DELL'ORCO, G et al.Fusion engineering and design. 2007, Vol 82, Num 15-24, pp 2164-2170, issn 0920-3796, 7 p.Conference Paper

Parametric neutronic analysis of HCLL blanket for DEMO fusion reactor utilizing vacuum vessel ITER FDR designJORDANOVA, J; FISCHER, U; PERESLAVTSEV, P et al.Fusion engineering and design. 2006, Vol 81, Num 19, pp 2213-2220, issn 0920-3796, 8 p.Article

Overview of the European union fusion nuclear technologies development and essential elements on the way to DEMOANDREANI, R; DIEGELE, E; GULDEN, W et al.Fusion engineering and design. 2006, Vol 81, Num 1-7, pp 25-32, issn 0920-3796, 8 p.Conference Paper

Evaluation of nuclear heating, tritium breeding and shielding efficiency of the DEMO HCLL breeder blanketJORDANOVA, J; FISCHER, U; PERESLAVTSEV, P et al.Fusion engineering and design. 2005, Vol 75-79, pp 963-967, issn 0920-3796, 5 p.Conference Paper

Performance of the TAURO blanket system associated with a liquid-metal cooled divertorGOLFIER, H; AIELLO, G; FÜTTERER, M. A et al.Fusion engineering and design. 2000, Vol 49-50, pp 559-565, issn 0920-3796Conference Paper

Ferritic―Martensitic steel Test Blanket Modules: Status and future needs for design criteria requirements and fabrication validationSALAVY, J.-F; AIELLO, G; POITEVIN, Y et al.Journal of nuclear materials. 2009, Vol 386-88, pp 922-926, issn 0022-3115, 5 p.Conference Paper

TRITIUM IN FUSION : R&D IN THE EULASSER, R; ANTIPENKOV, A; GABRIEL, F et al.Fusion science and technology. 2008, Vol 54, Num 1, pp 39-44, 6 p.Conference Paper

EU blanket design activities and neutronics support effortsFISCHER, U; BATISTONI, P; BOCCACCINI, L. V et al.Fusion science and technology. 2005, Vol 47, Num 4, pp 1052-1059, 8 p.Conference Paper

The helium-cooled lithium lead blanket test proposal in ITER and requirements on test blanket modules instrumentationLI PUMA, A; POITEVIN, Y; GIANCARLI, L et al.Fusion engineering and design. 2005, Vol 75-79, pp 951-955, issn 0920-3796, 5 p.Conference Paper

Further improvements of the water-cooled Pb-17Li blanketFÜTTERER, M. A; BENAMATI, G; VELLA, G et al.Fusion engineering and design. 2001, Vol 58-59, pp 523-527, issn 0920-3796Conference Paper

Potential and limits of water-cooled Pb-17Li blankets and divertors for a fusion power plantFÜTTERER, M. A; BARLEON, L; GIANCARLI, L et al.Fusion engineering and design. 2000, Vol 49-50, pp 543-549, issn 0920-3796Conference Paper

In vivo cancer gene therapy by adenovirus-mediated transfer of a bifunctional yeast cytosine deaminase/uracil phosphoribosyltransferase fusion geneERBS, P; REGULIER, E; KINTZ, J et al.Cancer research (Baltimore). 2000, Vol 60, Num 14, pp 3813-3822, issn 0008-5472Article

IFMIF specifications from the users point of viewGARIN, P; DIEGELE, E; SUGIMOTO, M et al.Fusion engineering and design. 2011, Vol 86, Num 6-8, pp 611-614, issn 0920-3796, 4 p.Conference Paper

Tritium control modelling for a helium cooled lithium-lead blanket of a fusion power reactorFARABOLINI, W; CIAMPICHETTI, A; SARDAIN, P et al.Fusion engineering and design. 2006, Vol 81, Num 1-7, pp 753-762, issn 0920-3796, 10 p.Conference Paper

HCLL TBM for ITER-design studiesRAMPAL, G; LI PUMA, A; POITEVIN, Y et al.Fusion engineering and design. 2005, Vol 75-79, pp 917-922, issn 0920-3796, 6 p.Conference Paper

The European breeding blankets development and the test strategy in ITERPOITEVIN, Y; BOCCACCINI, L. V; CARDELLA, A et al.Fusion engineering and design. 2005, Vol 75-79, pp 741-749, issn 0920-3796, 9 p.Conference Paper

Survey of in-vessel candidate materials for fusion power plants: the European materials R&D programmeGASPAROTTO, M; ANDREANI, R; POITEVIN, Y et al.Fusion engineering and design. 2003, Vol 66-68, pp 129-137, issn 0920-3796, 9 p.Conference Paper

Demo blanket technology R&D results in EUGASPAROTTO, M; BOCCACCINI, L. V; GIANCARLI, L et al.Fusion engineering and design. 2002, Vol 61-62, pp 263-271, issn 0920-3796, 9 p.Conference Paper

Modelisation of the mechanical behaviour of Breeding Blanket pebble bedsPOITEVIN, Y; DUCHESNE, A; EID, M et al.SOFT : Symposium on fusion technology. 1998, 2Vol, Vol 2, 1195-1198Conference Paper

Contact dose rates and relevant radioactive inventory in ITER TBM systemsZUCCHETTI, M; GUERRINI, L; POITEVIN, Y et al.Fusion engineering and design. 2011, Vol 86, Num 9-11, pp 2690-2693, issn 0920-3796, 4 p.Conference Paper

Development and qualification of functional materials for the EU Test Blanket Modules: Strategy and R&D activitiesZMITKO, M; POITEVIN, Y; BOCCACCINI, L et al.Journal of nuclear materials. 2011, Vol 417, Num 1-3, pp 678-683, issn 0022-3115, 6 p.Conference Paper

Development of welding technologies for the manufacturing of European Tritium Breeder blanket modulesPOITEVIN, Y; AUBERT, Ph; DIEGELE, E et al.Journal of nuclear materials. 2011, Vol 417, Num 1-3, pp 36-42, issn 0022-3115, 7 p.Conference Paper

Tritium breeder blankets design and technologies in Europe: Development status of ITER Test Blanket Modules, test & qualification strategy and roadmap towards DEMOPOITEVIN, Y; BOCCACCINI, L. V; GUERRINI, L et al.Fusion engineering and design. 2010, Vol 85, Num 10-12, pp 2340-2347, issn 0920-3796, 8 p.Conference Paper

Blanket manufacturing technologies : Thermomechanical tests on helium cooled lithium lead (HCLL) blanket mocks upLAFFONT, G; CACHON, L; TARAUD, P et al.Fusion engineering and design. 2008, Vol 83, Num 7-9, pp 1208-1211, issn 0920-3796, 4 p.Conference Paper

Potential performances of a divertor concept based on liquid metal cooled SiCf/SiC structuresLI PUMA, A; GIANCARLI, L; GOIFIER, H et al.Fusion engineering and design. 2003, Vol 66-68, pp 401-405, issn 0920-3796, 5 p.Conference Paper

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