Linkage synthesis : Topology selection fixed by dimensional constraints, study of an exampleSARDAIN, P.Mechanism and machine theory. 1997, Vol 32, Num 1, pp 91-102, issn 0094-114XArticle

Main safety issues at the transition from ITER to fusion power plants : Safety aspects of fusion power plantsGULDEN, W; CIATTAGLIA, S; MASSAUT, V et al.Nuclear fusion. 2007, Vol 47, Num 7, issn 0029-5515, S415-S421Conference 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

Consequences of Pb-17Li/water interaction within a blanket moduleSARDAIN, P; BENAMATI, G; RICAPITO, I et al.SOFT : Symposium on fusion technology. 1998, 2Vol, Vol 2, 1537-1540Conference Paper

Consequences of a loss of the condenser in the SEAFP reactorSARDAIN, P; GAILLARD, J. P; PORPORAT, M et al.SOFT : Symposium on fusion technology. 1998, 2Vol, Vol 2, 1541-1544Conference Paper

The TBM-CA configuration management approach for the ITER test blanket module - application to the HCLL TBSJOURD'HEUIL, L; PANAYOTOV, D; SALAVY, J.-F et al.Fusion engineering and design. 2011, Vol 86, Num 9-11, pp 2317-2321, issn 0920-3796, 5 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

European development of He-cooled divertors for fusion power plantsNORAJITRA, P; GINIYATULIN, R; NARDI, C et al.Nuclear fusion. 2005, Vol 45, Num 11, pp 1271-1276, issn 0029-5515, 6 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

On the use of tin-lithium alloys as breeder material for blankets of fusion power plantsFÜTTERER, M. A; AIELLO, G; BARBIER, F et al.Journal of nuclear materials. 2000, Vol 283-87, pp 1375-1379, issn 0022-3115, bConference 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

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

The EVITA programme : Experimental and numerical simulation of a fluid ingress in the cryostat of a water-cooled fusion reactorSARDAIN, P; AYRAULT, L; LAFFONT, G et al.Fusion engineering and design. 2005, Vol 75-79, pp 1265-1269, 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

Modelling of two-phase flow under accidental conditions fusion codes benchmarkSARDAIN, P; GIRARD, C; ANDERSSON, J et al.Fusion engineering and design. 2001, Vol 54, Num 3-4, pp 555-561, issn 0920-3796Conference Paper

The EU TBM systems: Design and development programmeBOCCACCINI, L. V; SALAVY, J.-F; BED, O et al.Fusion engineering and design. 2009, Vol 84, Num 2-6, pp 333-337, issn 0920-3796, 5 p.Conference Paper

Power conversion cycles study for he-cooled reactor concepts for DEMOMEDRANO, M; PUENTEB, D; SARDAIN, P et al.Fusion engineering and design. 2007, Vol 82, Num 15-24, pp 2689-2695, issn 0920-3796, 7 p.Conference Paper

Recent progress in DEMO fusion core engineering : Improved segmentation, maintenance and blanket conceptsIHLI, T; BOCCACCINI, L. V; JANESCHITZ, G et al.Fusion engineering and design. 2007, Vol 82, Num 15-24, pp 2705-2712, issn 0920-3796, 8 p.Conference Paper

The European Fusion Reactor ActivitiesMAISONNIER, D; CAMPBELL, D; WARD, C. D et al.Revue générale nucléaire. 2007, Num 1, pp 87-95, issn 0335-5004, 9 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