Radioactive aerosol disperses slightly via contamination prevention systems such as control enclosures and filters when the nuclear installation is dismantled, and it might impact the environment. Therefore, when decommissioning is planned, it is necessary to assess the safety such as exposure dose evaluation to the public. For the radioactive aerosol, it is possible that the dispersion ratio is different according to the contamination condition, the dismantlement method of the material, nuclides (elements), etc. The radiation exposure evaluation for the decommissioning plan has been executed by operators in Japan based on a number of experiments (mostly cold tests) and overseas results. The decommissioning is now being carried out at the Tokai Power Station (GCR) and Fugen Decommissioning Engineering Center in Japan. In this study, the results data is acquired at the decommissioning sites, and the methodology and data for the exposure dose evaluation are verified and confirmed. These examination results will lead to the upgrading and improvement of the exposure evaluation methodology. In particular, the dismantlement work of connected piping of the heat exchanger (steam generator) was executed in the Tokai Power Station in 2008. In this study, we paid attention to the radionuclides of Co-60 and Cs-137 that adhered to piping, and the dispersion behavior of aerosol was measured and contamination prevention effect was assured. As a result, the data show that the cesium concentrates about four times higher than cobalt. Moreover, the effects of the prevention measures of contamination were confirmed and the behavior of the radioactive aerosol became clear and the effective findings about the dose evaluation of the dismantling were collected.
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ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management
October 11–15, 2009
Liverpool, UK
Conference Sponsors:
- Nuclear Engineering Division and Environmental Engineering Division
ISBN:
978-0-7918-4408-3
PROCEEDINGS PAPER
Measurement of Radioactive Aerosol Behavior During Dismantling and Reflection to the Exposure Dose Evaluation
Yukihiro Iguchi,
Yukihiro Iguchi
Japan Nuclear Energy Safety Organization, Minato, Japan
Search for other works by this author on:
Masami Kato
Masami Kato
Japan Nuclear Energy Safety Organization, Minato, Japan
Search for other works by this author on:
Yukihiro Iguchi
Japan Nuclear Energy Safety Organization, Minato, Japan
Masami Kato
Japan Nuclear Energy Safety Organization, Minato, Japan
Paper No:
ICEM2009-16107, pp. 389-396; 8 pages
Published Online:
December 12, 2010
Citation
Iguchi, Y, & Kato, M. "Measurement of Radioactive Aerosol Behavior During Dismantling and Reflection to the Exposure Dose Evaluation." Proceedings of the ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management. ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management, Volume 2. Liverpool, UK. October 11–15, 2009. pp. 389-396. ASME. https://doi.org/10.1115/ICEM2009-16107
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