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Pb-17Li/water interaction in DEMO WCLL blanket: water micro-leaksRICAPITO, I; CIAMPICHETTI, A; BENAMATI, G et al.Fusion engineering and design. 2003, Vol 65, Num 4, pp 577-587, issn 0920-3796, 11 p.Article

Preliminary studies on PbO reduction in liquid pb-bi eutectic by flowing hydrogenRICAPITO, I; FAZIO, C; BENAMATI, G et al.Journal of nuclear materials. 2002, Vol 301, Num 1, pp 60-63, issn 0022-3115Conference Paper

Effect of hydrogen on the ductility reduction of F82H martensitic steel after different heat treatmentsBEGHINI, M; BENAMATI, G; BERTINI, L et al.Journal of nuclear materials. 2001, Vol 288, Num 1, pp 1-6, issn 0022-3115Article

Evaluation and mitigation of tritium memory in detritiation dryersMALARA, C; RICAPITO, I; EDWARDS, R. A. H et al.Journal of nuclear materials. 1999, Vol 273, Num 2, pp 203-212, issn 0022-3115Article

Status of the EU R&D programme on the blanket-shield modules for ITERLORENZETTO, P; BOIREAU, B; ROEDIG, M et al.Fusion engineering and design. 2008, Vol 83, Num 7-9, pp 1015-1019, issn 0920-3796, 5 p.Conference Paper

Mechanical and corrosion behaviour of EUROFER 97 steel exposed to Pb-17LiBENAMATI, G; FAZIO, C; RICAPITO, I et al.Journal of nuclear materials. 2002, Vol 307-11, pp 1391-1395, issn 0022-3115, 5 p., bConference 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

The ancillary systems of the European test blanket modules: Configuration and integration in TIERRICAPITO, I; BEDE, O; BOCCACCINI, L. V et al.Fusion engineering and design. 2010, Vol 85, Num 7-9, pp 1154-1161, issn 0920-3796, 8 p.Conference Paper

The coolant purification system of the European test blanket modules: Preliminary designCIAMPICHETTI, A; AIELLO, A; COCCOLUTO, G et al.Fusion engineering and design. 2010, Vol 85, Num 10-12, pp 2033-2039, issn 0920-3796, 7 p.Conference 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

Qualification of tritium permeation barriers in liquid Pb-17LiAIELLO, A; RICAPITO, I; BENAMATI, G et al.Fusion engineering and design. 2003, Vol 69, Num 1-4, pp 245-252, issn 0920-3796, 8 p.Conference Paper

A water cooled lithium-lead blanket without tritium permeation barriers: feasibility and economical analysisKVETON, O; RICAPITO, I; FUTTERER, M. A et al.Fusion engineering and design. 2001, Vol 58-59, pp 933-937, issn 0920-3796Conference Paper

Experimental tests and thermo-mechanical analyses on the HEXCALIBER mock-upDI MAIO, P. A; DELL'ORCO, G; GIAMMUSSO, R et al.Fusion engineering and design. 2008, Vol 83, Num 7-9, pp 1287-1293, issn 0920-3796, 7 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

Tritium processing systems for the helium cooled pebble bed test blanket moduleRICAPITO, I; CIAMPICHETTI, A; AGOSTINI, P et al.Fusion engineering and design. 2008, Vol 83, Num 10-12, pp 1461-1465, 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

Comparative analysis of tritium recovery methods from Pb-17Li water-cooled blanketDWORSCHAK, H; MALARA, C; RICAPITO, I et al.Fusion technology. 1995, Vol 28, Num 3, pp 578-585, issn 0748-1896, 1Conference 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

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

Steady state and transient thermal-hydraulic characterization of full-scale ITER divertor plasma facing componentsTINCANI, A; DI MAIO, P. A; DELL'ORCO, G et al.Fusion engineering and design. 2008, Vol 83, Num 7-9, pp 1034-1037, issn 0920-3796, 4 p.Conference Paper

Water large leaks into liquid Pb-17Li: first experimental results on LIFUS 5 facilityCIAMPICHETTI, A; RICAPITO, I; AIELLO, A et al.Fusion engineering and design. 2003, Vol 69, Num 1-4, pp 563-567, issn 0920-3796, 5 p.Conference Paper

Hydrogen isotopes permeability in eurofer 97 martensitic steelAIELLO, A; RICAPITO, I; BENAMATI, G et al.Fusion science and technology. 2002, Vol 41, Num 3, pp 872-876, 5 p., 2Conference Paper

Quantitative analysis of hydrogen isotopes with a mordenite column at 173 K by radio gas chromatographyWENDEL, J; WERTENBACH, H; GLUGLA, M et al.Fusion technology. 1995, Vol 28, Num 3, pp 1090-1094, issn 0748-1896, 2Conference Paper

TRITIUM EXTRACTION SYSTEMS FOR THE EUROPEAN HCLL/HCPB TBMsRICAPITO, I; CIAMPICHETTI, A; BENAMATI, G et al.Fusion science and technology. 2008, Vol 54, Num 1, pp 107-112, 6 p.Conference Paper