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| Main Author: | |
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| Format: | Artículo científico |
| Language: | en |
| Published: |
Sociedade Brasileira de Proteção Radiológica - SBPR
2020
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| Online Access: | https://www.redalyc.org/articulo.oa?id=722280907011 |
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Table of Contents:
- Determination of dose rate during the inspection of spent fuel element in the testing cell Amr Abdelhady Biología 1 code ORIGEN2 hot cell MCNP code dose rate Testing cell is a multi-purpose shielded hot cell in open pool type reactor and one of its uses is inspecting the irradiated fuel element. Inspecting the irradiated fuel element may rise the radiation dose around the testing cell to level might be higher than the permissible limit. So, evaluating the predicted dose rate around the cell must be determined before the inspecting process. The dose rate level depends mainly on the decay time of the irradiated fuel element and the fuel burn-up. In this regard, a MCNP5 model was performed to simulate the irradiated fuel element inside the testing cell to estimate the radiation dose level around it during the inspection process. The dose rate would be estimated for different fuel burn-up and decay times. The calculations determine the minimal decay times required to manipulate the irradiated fuel element for burn-up ranging between 18745 and 101224.4 MWD/TU. 2020 artículo científico 2319-0612 https://www.redalyc.org/articulo.oa?id=722280907011 en http://www.redalyc.org/revista.oa?id=7222 Brazilian Journal of Radiation Sciences application/pdf Sociedade Brasileira de Proteção Radiológica - SBPR Brazilian Journal of Radiation Sciences (Brasil) Num.3 Vol.8