Protocol for characterization of clay as a backfill and coverage layers for near surface repository

Daisy Mary Marchezini dos Santos; Clédola Cássia Oliveira de Tello

doi:10.15392/bjrs.v7i2A.717

Autores/as

Daisy Mary Marchezini dos Santos Centro de Desenvolvimento da Tecnologia Nuclear
Clédola Cássia Oliveira de Tello Centro de Desenvolvimento da Tecnologia Nuclear

DOI:

https://doi.org/10.15392/bjrs.v7i2A.717

Palabras clave:

bentonite, repository, radioactive waste, RBMN Project

Resumen

The Radioactive Waste Management includes the operations since generation of the waste until its storage in repository, ensuring the protection of human beings and the environment from the possible negative impacts. The radioactive waste is segregated, treated, conditioned in suitable packages for posterior storage or disposal in repository. The “RBMN Project” objective is to implement the repository for the disposal of low and intermediate level radioactive wastes generated by nuclear activities in Brazil, proposing a definitive solution for their storage. Engineered and natural barriers as the backfill and coverage layers will compose the disposal system of a near surface repository, concept proposed by the “RBMN Project”. The use of these barriers aims to avoid or restrict the release of radionuclides from the waste to the human beings and environment. The waterproofing barriers are composed of clays. Certainly, for the national repository, will be used those clays existing in the place where it will be constructed. Them some basic tests will have to be carried out to verify the suitability of these clays as barriers. These tests were determined and performed with reference clay, a Brazilian bentonite constituted of 67.2% montmorillonite. The results were compared with national and international literature of materials with similar mineralogical features. The values found with 95% of confidence interval were 9.73±0,35 µm for granulometric size; 13,3±0,6% for the moisture content and 816±9 mmol.kg^-1 for the capacity of cationic exchange. A protocol for characterization of clay was elaborated presenting these tests for it future use.

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Biografía del autor/a

Daisy Mary Marchezini dos Santos, Centro de Desenvolvimento da Tecnologia Nuclear

PhD student in Radiation, Minerals and Materials Science and Technology, CDTN (2021). Master's degree in Radiation Science and Technology, Minerals and Materials by the CDTN (2017), graduation in Chemistry Degree from the University of Itaúna (2009). Your research interests include radioactive wastes and their deposits. Currently she is part of the staff of the SEGRE / CDTN sector.
Clédola Cássia Oliveira de Tello, Centro de Desenvolvimento da Tecnologia Nuclear

Graduation in Chemical Engineering from the School of Engineering (1977), a Master's degree in Nuclear Engineering from the Federal University of Minas Gerais (1987) and a PhD in Chemical Engineering from the State University of Campinas (2001). She is currently a member of the National Nuclear Energy Commission, an expert - International Atomic Energy Agency and senior technologist of the National Nuclear Energy Commission. Technical Coordinator of the RBMN Project, whose objective is to implant and build the national repository for low and intermediate level radioactive waste.

Referencias

CNEN - Comissão Nacional de Energia Nuclear. Quem somos. Rio de Janeiro, Brazil, 2017. Available at: <http://www.cnen.gov.br/quem-somos>. Last accessed 30 Nov. 2017.

CNEN - Comissão Nacional de Energia Nuclear, CNEN-NN-8.01: Gerência de Rejeitos Radioativos de Baixo e Médio Níveis de Radiação. Resolução 167/14, CNEN, Rio de Janeiro, 2014. 45p

CNEN - Comissão Nacional de Energia Nuclear, CNEN-NN-8.02: Licenciamento de Depó-sitos de Rejeitos Radioativos de Baixo e Médio Níveis de Radiação. Resolução 168/14. Rio de Janeiro, 2014. 32p

CNEN – Comissão Nacional de Energia Nuclear, CNEN-NE-6.06: Seleção e escolha de lo-cais para depósitos de rejeitos radioativos. Resolução 014/89. Rio de Janeiro, 1990. 14p

CNEN - Comissão Nacional de Energia Nuclear, CNEN-NN-6.09: Critérios de aceitação para deposição de rejeitos radioativos de baixo e médio níveis de radiação. Resolução 012/02. Rio de Janeiro, 2002. 11p

CNEN - Comissão Nacional de Energia Nuclear: Nuclear Safety Glossary. Rio de Janeiro, Brazil: CNEN. 2012. Available at: <http://www.cnen.gov.br/seguranca/normas/pdf/glossario_ingles.pdf>. Last accessed: 30 Nov. 2017.

IAEA - International Atomic Energy Agency. Disposal of radioactive waste (Safety Stan-dards Series, Requirements, No. SSR-5), Vienna: IAEA, 2011. 83p.

IAEA - International Atomic Energy Agency. Classification of radioactive waste General Safety Guide series, No. GSG-1), Vienna: IAEA, 2009. 68p.

IAEA - International Atomic Energy Agency. Performance of engineered barrier materials in near surface disposal facilities for radioactive waste (TECDOC-1255), Vienna: IAEA, 2001. 56p.

SANTOS, D. M. M. Elaboração de protocolo para caracterização de argilas como mate-rial de recheio e de cobertura para repositório de superfície. Dissertação de Mestrado em Ciência e Tecnologia das Radiações, Minerais e Materiais, Belo Horizonte: Centro de Desenvolvimento da Tecnologia Nuclear, 2017. 111p.

TELLO, C. C. O. Status of the Implementation of Brazilian National Repository, In: IN-TERNATIONAL NUCLEAR ATLANTIC CONFERENCE, 2015, São Paulo. Annals… São Paulo: Comissão Nacional de Energia Nuclear, 2015.

IAEA- International Atomic Energy Agency. Upgrading of near surface repositories for radioactive waste (Technical reports series, No. 433), Vienna: IAEA, 2005. 147p.

OECD - Organisation for Economic Co-Operation and Development/Nuclear Energy Agency. Low-Level Radioactive Waste Repositories: An Analysis of Costs. Paris, France: OECD. 1999. Available at:<http://www.oecd-ilibrary.org/nuclear-energy/low-level-radioactive-waste-repositories_9789264172029-en>. Last accessed 30 Nov. 2017.

TELLO, C.C.O. Efetividades das Bentonitas na retenção de césio em produtos de Rejeitos Cimentados, Tese de Doutorado em Engenharia Química, Campinas: FEQ/UNICAMP, 2001. 167p.

IAEA - International Atomic Energy Agency. Characterization of swelling clays as compo-nents of the engineered barrier system for geological repositories (TECDOC-1718), Vienna, Austria: IAEA, 2013. 118p.

DNPM – Departamento Nacional de Produção Mineral. Sumário Mineral 2015, Brasília: DNPM, 2016. 30p. Available at: <http://www.dnpm.gov.br/dnpm/sumarios/sumario-mineral-2015/view>. Last accessed: 30 Nov 2017.

SILVA, T. V.; HAUCZ, M. J. A. Determinação do teor de umidade em argilas, Rotina Téc-nica RT(SN1)CDTN-0417, Belo Horizonte, Brazil (2005). 5p

SANTOS, D. M. M., TELLO, C. C. O. Establishment Of Characterizing Parameters Of Clay As A Filling Material And Coverage For Repository, In: INTERNATIONAL NUCLEAR AT-LANTIC CONFERENCE, 2015, São Paulo. Annals… São Paulo: Comissão Nacional de Energia Nuclear, 2015.

FREIRE, C. B.; HAUCZ, M. J. A.; TELLO, C. C. O. Determinação da capacidade de troca catiônica (CTC) de argilas utilizando o método da adsorção de azul de metileno (AAM). Nota Informativa – NI LABCIM - SEGRE/CDTN, Belo Horizonte, Brazil, 2012, 7p.

ASTM - American Society for Testing and Materials. Standard Test Method for Methylene Blue Index of Clay. C837-14. 2014. p. 01-02.

SANTOS, L. V.; POLIVANOV, H.; ALAMINO, R. C. J.; SILVA, V. H. G. Adsorção de Cloreto e Potássio em Solos Tropicais. Rio de Janeiro: IGEO, v. 29, p.20. 2006. Available at: < http://www.ppegeo.igc.usp.br/index.php/anigeo/article/view/4871>. Last accessed: 30 Nov. 2017.

PINTO, C. S. Curso Básico de Mecânica dos Solos. 3rd Ed. São Paulo: Oficina de Textos, 2006.

ASTM - American Society for Testing and Materials. Standard Test Methods for Labora-tory Compaction Characteristics of Soil Using Modified Effort (56,000 ft-lbf/ft3 (2,700 kN-m/m3)). D1557-12. 2012. p.01-14.

ABNT - Associação Brasileira de Normas Técnicas. Solo: Ensaio de compactação. NBR 7182. 1986. p.1-10.