Lessons Learned: a knowledge management tool for learning about radiation accidents

Authors

  • Luis Carlos Jansen Silva INSTITUTE OF RADIATION PROTECTION AND DOSIMETRY
  • Fernando Barcellos Razuck INSTITUTE OF RADIATION PROTECTION AND DOSIMETRY

DOI:

https://doi.org/10.15392/bjrs.v8i3A.1353

Keywords:

lessons learned, nuclear knowledge management, bibliographical review, postgraduate course on radiation protection, International Atomic Energy Agency

Abstract

According to the International Atomic Energy Agency (IAEA), the lessons learned (LL) in a radiation accident are extremely important in the building of learning about accidents, identifying best practices and preventing new accidents from occurring – making that if they do, the damage could be mitigated. Thereby, it was noted that the problems identified from the accident analysis led to the adoption of a series of measures to make facilities safer and more prepared for such accidents. Thus, is evident that the analysis of the LL about radiation accidents is a powerful learning tool in the field of radiation protection, opening space for discussions of a wider knowledge about nuclear energy. It is then observed the importance of evaluating LL to strengthen the Nuclear Knowledge Management (NKM). In this sense, the objective of this paper is to demonstrate to students of a Postgraduate course on Radiation Protection how to carry out a bibliographical review on the accidents involving radiation material, based in the main publications of the IAEA about LL. It is understood that, in relation to the dissemination of knowledge, the analysis of the LL as a tool for NKM is of extra relevance, not only for studies and learning in the area, but mainly for the prevention of accidents.

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References

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Published

2021-02-09

How to Cite

Silva, L. C. J., & Razuck, F. B. (2021). Lessons Learned: a knowledge management tool for learning about radiation accidents. Brazilian Journal of Radiation Sciences, 8(3A (Suppl.). https://doi.org/10.15392/bjrs.v8i3A.1353

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Section

XXI Meeting on Nuclear Reactor Physics and Thermal Hydraulics (XXI ENFIR) and VI ENIN