Selection of steel fibers dosage in concrete for repository containers

Authors

  • Carolina Nogueira da Silva Centro de Desenvolvimento da Tecnologia Nuclear
  • Clédola Cássia Oliveira de Tello Centro de Desenvolvimento da Tecnologia Nuclear

DOI:

https://doi.org/10.15392/bjrs.v9i1A.1527

Keywords:

steel fibers, Steel Fiber Reinforcement Concrete, repository, concrete containers

Abstract

The use of nuclear energy, as well as all human activity, generates wastes and these need to receive suitable treatments so that they don’t expose a risk to the public and the environment. Currently there is a project in Brazil whose objective is the implementation of a national repository for the final storage of low and intermediate level waste. The disposal of the radioactive waste is based on the concept of multiple barriers, in which packed wastes are conditioned in concrete containers, which are then placed in modules, which are closed and covered by natural materials. In this work, Steel Fiber Reinforced Concrete (SFRC) was studied as a substitute for the concrete with conventional steel reinforcement in the production of containers. Compressive and tensile strength tests were performed, as well as characterization and evaluation of steel fibers. 48 specimens of concrete were prepared with two types of fibers (A and C) and tested. The best results were obtained with the addition of 1.5% vol. of type A fibers. Through the carbon and sulfur quantification test it was possible to conclude the steel used in the fibers’ manufacture was low carbon. It was also possible to verify, using the folding test, the material used served the parameters of quality. This research project was supported by the Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), the Comissão Nacional de Energia Nuclear (CNEN) and the Fundação de Amparo à Pesquisa do Estado de Minas Gerais (FAPEMIG).

Downloads

Download data is not yet available.

Author Biographies

Carolina Nogueira da Silva, Centro de Desenvolvimento da Tecnologia Nuclear

Aluna de Iniciação do CDTN no Serviço de Gerência de Rejeitos entre 03/2018 e 07/2019 e atualmente mestranda no Serviço de Tecnologia Mineral

Clédola Cássia Oliveira de Tello, Centro de Desenvolvimento da Tecnologia Nuclear

Tecnologista no Serviço de Gerência de Rejeitos

References

TELLO, C.C.O. “Implementation of the Brazilian national repository”. INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, Recife, 2013.

MEHTA, P.K.; MONTEIRO, P.J.M. Concreto: estrutura, propriedades e materiais. Editora Pini Ltda, São Paulo, Brasil, 1994.

SHIMOSAKA, T.J. Influência do teor de diferentes tipos de fibras de aço em concretos autoa-densáveis. Programa de Pós Graduação em Engenharia Civil da Universidade Tecnológica Federal do Paraná, Pato Branco, 123p, 2017.

FIGUEIREDO, A. D. Concreto Reforçado Com Fibras. Livre Docência, p. 246, 2011.

ASSOCIAÇÃO BRASILEIRA DE NORMAS TÉCNICAS (ABNT). NBR 15530: Fibras de aço para concreto- Especificação. Rio de Janeiro, 7p, 2007.

FIGUEIREDO, A. D. A nova especificação brasileira das fibras de aço para concreto. CONGRESSO BRASILEIRO DO CONCRETO, Salvador, Brasil, pp. 1–11, 2008.

RODRIGUES, P.P.F. Parâmetros de dosagem do concreto. ET- 67. Associação Brasileira de Cimento Portland, São Paulo, 1990.

ASSOCIAÇÃO BRASILEIRA DE NORMAS TÉCNICAS (ABNT). NBR 5739: Concreto- Ensaio de compressão de corpos de prova cilíndricos. Rio de Janeiro, 9p , 2018.

ASSOCIAÇÃO BRASILEIRA DE NORMAS TÉCNICAS (ABNT). NBR 7222: Concreto e argamassa- Determinação da resistência à tração por compressão diametral de corpos de prova cilíndricos. Rio de Janeiro, 5p, 2011.

ARCELORMITTAL. Guia do Aço. Brazil, 2019. Available at: <https://brasil.arcelormittal.com/pdf/produtos-solucoes/catalogos/catalogo-guia-aco.pdf?asCatalogo=pdf>. Last accessed: 22 June 2020.

Downloads

Published

2021-04-30

How to Cite

Silva, C. N. da, & Tello, C. C. O. de. (2021). Selection of steel fibers dosage in concrete for repository containers. Brazilian Journal of Radiation Sciences, 9(1A). https://doi.org/10.15392/bjrs.v9i1A.1527

Issue

Section

The Meeting on Nuclear Applications (ENAN) 2019