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Les modules de test de couverture tritigène : un pas vers l'autosuffisance en tritium = Test Blanket Modules : a Step toward Fuel ProductionGIANCARLI, L.Revue générale nucléaire. 2007, Num 1, pp 67-68, issn 0335-5004, 2 p.Conference Paper

Status of tritium permeation barrier development in the EUKONYS, J; AIELLO, A; BENAMATI, G et al.Fusion science and technology. 2005, Vol 47, Num 4, pp 844-850, 7 p.Conference Paper

TRITIUM TRANSFERS EVALUATION ON ITER HCLL TBMGASTALDI, O; AIZES, P; GABRIEL, F et al.Fusion science and technology. 2008, Vol 54, Num 1, pp 101-106, 6 p.Conference Paper

A 2D finite element modelling of tritium permeation for the HCLL DEMO blanket moduleGABRIEL, F; ESCURIOL, Y; DABBENE, F et al.Fusion engineering and design. 2007, Vol 82, Num 15-24, pp 2204-2211, issn 0920-3796, 8 p.Conference Paper

Breeding Blanket Modules testing in ITER : An international program on the way to DEMOGIANCARLI, L; CHUYANOV, V; ABDOU, M et al.Fusion engineering and design. 2006, Vol 81, Num 1-7, pp 393-405, issn 0920-3796, 13 p.Conference Paper

Breeding blanket design and systems integration for a helium-cooled lithium-lead fusion power plantLI PUMA, A; BERTON, J. L; RABOIN, S et al.Fusion engineering and design. 2006, Vol 81, Num 1-7, pp 469-476, issn 0920-3796, 8 p.Conference Paper

Issues and advances in SiCf/SiC composites development for fusion reactorsRICCARDI, B; GIANCARLI, L; HASEGAWA, A et al.Journal of nuclear materials. 2004, Vol 329-33, pp 56-65, issn 0022-3115, 10 p., aConference 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

Overview of EU activities on DEMO liquid metal breeder blanketsGIANCARLI, L; BENAMATI, G; MALANG, S et al.Fusion engineering and design. 1995, Vol 27, pp 337-352, issn 0920-3796Conference Paper

Tritium confinement requirements for the water-cooled Pb-17Li blanket for DEMOFÜTTERER, M. A; SEDANO, L. A; GIANCARLI, L et al.Fusion technology. 1995, Vol 28, Num 3, pp 614-618, issn 0748-1896, 1Conference Paper

A water cooled, lithium lead breeding blanket for a DEMO fusion reactorCASINI, G; LABBE, P; QUINTRIC-BOSSY, J et al.Fusion engineering and design. 1991, Vol 14, Num 3-4, pp 353-372, issn 0920-3796, 20 p.Article

ITER plasma-facing componentsMEROLA, Mario; LOESSER, D; PALMER, J et al.Fusion engineering and design. 2010, Vol 85, Num 10-12, pp 2312-2322, issn 0920-3796, 11 p.Conference Paper

Conceptual design of the blanket mechanical attachment for the helium-cooled lithium-lead reactorBARRERA, G; BRANAS, B; SARDAIN, P et al.Fusion engineering and design. 2008, Vol 83, Num 1, pp 6-20, issn 0920-3796, 15 p.Article

Design approach for the main ITER test blanket modules for the EU helium cooled lithium-lead blanketsRAMPAL, G; GATELET, D; GIANCARLI, L et al.Fusion engineering and design. 2006, Vol 81, Num 1-7, pp 695-700, issn 0920-3796, 6 p.Conference Paper

Conceptual design of a high temperature water-cooled divertor for a fusion power reactorGIANCARLI, L; BONAL, J. P; LI PUMA, A et al.Fusion engineering and design. 2005, Vol 75-79, pp 383-386, 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

Optimization of a water-cooled divertor for the European power plant conceptual studyLI PUMA, A; GIANCARLI, L; POITEVIN, Y et al.Fusion engineering and design. 2002, Vol 61-62, pp 177-183, issn 0920-3796, 7 p.Conference Paper

R&D issues for SiCf/SiC composites structural material in fusion power reactor blanketsGIANCARLI, L; AIELLO, G; CASO, A et al.Fusion engineering and design. 2000, Vol 48, Num 3-4, pp 509-520, issn 0920-3796Conference Paper

Candidate blanket concepts for a European fusion power plant studyGIANCARLI, L; FERRARI, M; FÜTTERER, M. A et al.Fusion engineering and design. 2000, Vol 49-50, pp 445-456, issn 0920-3796Conference Paper

Status of the European R&D activities on SiCf/SiC composites for fusion reactorsRICCARDI, B; FENICI, P; FRIAS REBELO, A et al.Fusion engineering and design. 2000, Vol 51-52, pp 11-22, issn 0920-3796Conference Paper

Design requirements for SiC/SiC composites structural material in fusion power reactor blanketsGIANCARLI, L; BONAL, J. P; CASO, A et al.Fusion engineering and design. 1998, Vol 41, Num 1-4, pp 165-171, issn 0920-3796Conference Paper

Current material and design studies for the utilization of Li2ZrO3 in the BIT blanket conceptROUX, N; MOUGIN, J; RASNEUR, B et al.Journal of nuclear materials. 1994, Vol 212-15, Num B, pp 862-867, issn 0022-3115Conference Paper

The HCLL Test Blanket Module system : Present reference design, system integration in ITER and R&D needsSALAVY, J.-F; AIELLO, G; RAMPAL, G et al.Fusion engineering and design. 2008, Vol 83, Num 7-9, pp 1157-1162, issn 0920-3796, 6 p.Conference Paper

Power plant conceptual studies in EuropeMAISONNIER, D; CAMPBELL, D; SARDAIN, P et al.Nuclear fusion. 2007, Vol 47, Num 11, pp 1524-1532, issn 0029-5515, 9 p.Article

In-vessel component designs for a self-cooled lithium-lead fusion reactorGIANCARLI, L; BÜHLER, L; SZCZEPANSKI, J et al.Fusion engineering and design. 2003, Vol 69, Num 1-4, pp 763-768, issn 0920-3796, 6 p.Conference Paper

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