An experimental study on Sodalite and SAP matrices for immobilization of spent chloride salt waste

JOURNAL OF NUCLEAR MATERIALS

卷:499

Article

Giacobbo, Francesca¹  Da Ros, Mirko¹  Macerata, Elena¹  Mariani, Mario¹  Giola, Marco¹  De Angelis, Giorgio²  Capone, Mauro³  Fedeli, Carlo³ 

[1] Politecn Milan, Dipartimento Energia, Sez Ingn Nucl, Piazza L da Vinci 32, I-20133 Milan, Italy

[2] ENEA, CR Casaccia, Unita Tecn Tecnol & Impianti Fiss & Gest Mat Nucl, Via Anguillarese 301, I-00123 Rome, Italy

[3] ENEA, CR Casaccia, Dipartimento Fus & Tecnol Sicurezza Nucl, Via Anguillarese 301, I-00123 Rome, Italy

关键词: Nuclear fuel cycle;    Pyro-processing;    Chloride salt waste;    Sodalite;    SAP;    Ceramic wasteforms;    Leaching tests;   

DOI  :  10.1016/j.jnucmat.2017.11.051

来源: Elsevier

【 摘 要 】

In the frame of Generation IV reactors a renewed interest in pyro-processing of spent nuclear fuel is underway. Molten chloride salt waste arising from the recovering of uranium and plutonium through pyro-processing is one of the problematic wastes for direct application of vitrification or ceramization. In this work, Sodalite and SAP have been evaluated and compared as potential matrices for confinement of spent chloride salt waste coming from pyro-processing. To this aim Sodalite and SAP were synthesized both in pure form and mixed with different glass matrices, i.e. commercially available glass frit and borosilicate glass. The confining matrices were loaded with mixed chloride salts to study their retention capacities with respect to the elements of interest. The matrices were characterized and leached for contact times up to 150 days at room temperature and at 90 degrees C. SEM analyses were also performed in order to compare the matrix surface before and after leaching. Leaching results are discussed and compared in terms of normalized releases with similar results reported in literature. According to this comparative study the SAP matrix with glass frit binder resulted in the best matrix among the ones studied, with respect to retention capacities for both matrix and spent fuel elements. (c) 2017 Elsevier B.V. All rights reserved.

【 授权许可】

Free