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A study on sodalite pellets as matrix for spent chloride saltsconfinement

Published online by Cambridge University Press:  20 February 2017

M. Capone,
C. Fedeli,
G. De Angelis,
M. Da Ros,
F. Giacobbo,
M. Giola,
E. Macerata and
M. Mariani
M. Capone
Affiliation:
ENEA, CR Casaccia, Dipartimento Fusione e Tecnologie per la Sicurezza Nucleare, Via Anguillarese 301, 00123 S. Maria di Galeria, Roma, Italy
C. Fedeli
Affiliation:
ENEA, CR Casaccia, Dipartimento Fusione e Tecnologie per la Sicurezza Nucleare, Via Anguillarese 301, 00123 S. Maria di Galeria, Roma, Italy
G. De Angelis
Affiliation:
Retired from ENEA, CR Casaccia, Unità Tecnica Tecnologie e Impianti per la Fissione e la Gestione del Materiale Nucleare, Via Anguillarese 301, 00123 S. Maria di Galeria, Roma, Italy
M. Da Ros
Affiliation:
Politecnico di Milano, Dipartimento di Energia, Sezione Ingegneria Nucleare, Piazza L. da Vinci 32, 20133 Milano, Italy
F. Giacobbo*
Affiliation:
Politecnico di Milano, Dipartimento di Energia, Sezione Ingegneria Nucleare, Piazza L. da Vinci 32, 20133 Milano, Italy
M. Giola
Affiliation:
Politecnico di Milano, Dipartimento di Energia, Sezione Ingegneria Nucleare, Piazza L. da Vinci 32, 20133 Milano, Italy
E. Macerata
Affiliation:
Politecnico di Milano, Dipartimento di Energia, Sezione Ingegneria Nucleare, Piazza L. da Vinci 32, 20133 Milano, Italy
M. Mariani
Affiliation:
Politecnico di Milano, Dipartimento di Energia, Sezione Ingegneria Nucleare, Piazza L. da Vinci 32, 20133 Milano, Italy
*
*(Email: francesca.giacobbo@polimi.it)
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Abstract

Pellets made of pure sodalite blended with commercial glass frit and pellets madeof sodalite, glass frit and a mixture of chloride salts, synthesized through drypressing and subsequent thermal treatment, were evaluated as a potential matrixfor confinement of spent chloride salts coming from pyroprocesses. The sodalitepellets were leached at 23°C and 90°C for 28 days, accordingto the ASTM C1220-10 procedure. Normalized release rates were estimated for thefollowing elements: Li, Na, Al, Si, K, Rb, Cs, Sr, Ba, La, Nd and compared withliterature results. SEM investigations, carried out before and after theleaching tests, show dissolution and re-precipitation phenomena at90°C.

Keywords

ceramicwaste managementCl

Information

Type
Articles
Information
MRS Advances , Volume 1 , Issue 63-64: Scientific Basis for Nuclear Waste Management XXXIX , 2016, pp. 4261 - 4267
Copyright
Copyright © Materials Research Society 2017 

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References

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