Abstract
The new sipping device constructed at Centro de Desenvolvimento da Tecnologia Nuclear—CDTN (Nuclear Technology Development Center—CDTN), Belo Horizonte, Brazil will be used to inspect irradiated fuel elements cladding in the IPR-R1 TRIGA reactor. The sipping test method is important to check the integrity of the irradiated fuel elements cladding of this reactor, which may be affected by corrosion over long periods of time. The sipping test identifies failed fuel elements by measuring Cs-137 radioactive metal ion activity in the surrounding water, collected via the sipping device. This chapter describes the application of the “what if” technique for assessing risk and reliability in sipping test operations, including an analysis to identify human error and equipment failure modes. Results show initiating events, consequences, and recommended safeguards. In addition, measures to reduce human error are also provided. Human error has been identified as the primary cause or contributing factor in failure modes.
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Acknowledgments
This study was supported and funded by the following organizations: Nuclear Technology Development Center, Brazilian Nuclear Energy Commission (CNEN), Research Support Foundation of the State of Minas Gerais (FAPEMIG), Brazilian Council for Scientific and Technological Development (CNPq), and Coordination for Improvement of Higher Education of Personnel (CAPES).
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Gual, M.R., Rodrigues, R.R., de Oliveira, V., Cunha, C.L. (2018). Prevention of Human Factors and Reliability Analysis in Operating of Sipping Device on IPR-R1 TRIGA Reactor, a Study Case. In: De Felice, F., Petrillo, A. (eds) Human Factors and Reliability Engineering for Safety and Security in Critical Infrastructures. Springer Series in Reliability Engineering. Springer, Cham. https://doi.org/10.1007/978-3-319-62319-1_6
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