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S. Casadio, F. Orlandini, Oscillopolarographic reduction of uranyl ions at mercury electrode in acidic
nitrate media, Electrochimica Acta 17(1972)441-444
S. Casadio, L. Lorenzini, Cyclic Voltammetry behaviour of uranyl ion in sulphuric acid solutions.
Application to some nuclear materials characterization, Analytical Letters 6(1973)808-820
S. Casadio, F. Orlandini, Double layer effect on the electrode kinetic reduction of Pu(IV) carbonate
complexes in aqueous solution, J. Inorg. Nucl. Chemistry 34(1972)3845
Cyclic voltammetry for mixed diffusion-charge transfer control of simple anodic dissolution and
passivation of the electrode material. Journal of Electroanalytical Chemistry and Interfacial
Electrochemistry, Volume 72, Issue 2, 10 September 1976, Pages 243-250. S. Casadio

Nell’ambito delle attività sui programmi internazionali pubblicai tanti lavori fatti in “equipe” con la
collaborazione di molti esperti utilizzando impianti complessi in reattori nucleari da ricerca ben attrezzati. Il
ruolo originale e trainante da parte Casaccia era essenzialmente pilotato dal giovane Carlo Alvani che
letteralmente “fabbricava” i provini ceramici con precisione usando processi innovativi ed efficaci, e ne
caratterizzava in modo perfetto le interazioni con i gas di processo previsti per le applicazioni di questi
materiali (Temperature Programmed -Desorption (TPD), -Oxidation (TPO), -Reduction (TPR), ed infine –
Tritium Release). Gli altri ricercatori e tecnici del mio gruppo provvedevano alle caratterizzazioni chimiche,
fisiche, strutturali e microstrutturali e termiche dei materiali. Dopo il 2000 ci dedicammo a collaborare con i
giapponesi sul titanato di litio. La maggior parte dei lavori (una ventina) furono pubblicati sul “Journal of
Nuclesr Materials” (JNM), giornale per il quale ho aiutato il referee L.K. Mansur. Anche “Fusion
Engineering and Design” accolse altrettanti nostri contributi.

DOC - 1 Prima pagina della “relazione” tenuta a Parigi (CEA-sede) alla commissione dell’ European
Fusion Technology Program Helium Cooled Pebble Bed DEMO Blanket sui risultati ottenuti da
irraggiamenti in reattori veloci:

Irradiation behavior of Li-Ceramic Breeders - Review of Fast Reactor Irradiation Data
Sergio Casadio (ENEA-CR Casaccia, Via Anguillarese 301, 00060 S.M. di Galeria - Roma (Italy))
1 - Introduction
On May 1999 L. R. Greenwood (Pacific Northwest National Laboratory operated by US DOE by Battelle
Memorial Institute) reported the “Radiation Damage Calculation for the FUBR and BEATRIX irradiations of
Lithium Compounds in EBR-II and FFTF” (PNNL-12200). This paper is a remake of a re-view document
prepared years ago for the European HCPB Blanket project by taking into account the displacement damage
for lithium compounds irradiated in high flux fast experimental neutron reactors. These calculated data are
here accompanying the main experimental results by this unique “irradiation history” of the Li-ceramic
pellets and pebbles tested in neutron source-devices not more available today.
1.1- Historical
At the end of seventies the US efforts in promoting commercial fusion power plant In US culminated in the
STARFIRE study (1980)[i]. Lithium ceramics (LiAlO2 as prototype) were considered for tritium breeding in
the blanket. The conditions to recover the generated tritium were soon identified and the miniaturized full
process demonstrated to safely work (TRIO experiment [ii]). An irradiation program was launched to test
several candidates and to support blanket designing, the main critical technological issues having been
identified (FINESSE [iii]). Testing of Li2O, LiAlO2, Li4SiO4, Li2ZrO3 ceramics in fast neutrons (EBR-II
reactor) had already been performed at significant burnup (FUBR-1A) when EU program was not yet started
(1982). On November 1985 the IEA Implementing Agreement for a Program of Research and Development
on Radiation Damage in Fusion Materials promoted an “over the world” collaborative program (BEATRIX-
I, Breeder Exchange Matrix) in the frame of which all the studied Li-ceramics (including the EU candidates)
were tested in fast neutron up to large Li-burnups (FUBR-1B experiment).
On 1989 a plan was proposed by US (BEATRIX-II) to focus the efforts in solid breeder testing in the Fast
Flux Test Facility (FFTF). A MOTA device was especially designed for in-situ measuring tritium release
under irradiation to large burnups. EU countries refused to share the costs, looking at PHENIX as the