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Occupational Radiation Doses to Workers Transporting Spent Nuclear Fuel by Using Metal Overpack KCI 등재 SCOPUS
- 언어ENG
- URLhttps://db.koreascholar.com/Article/Detail/438725
pp.523-538
The transportation of spent nuclear fuel between management stages is expected, and the transportation workers may be exposed to radiation. When transporting spent nuclear fuel, the ALARA principle must be observed for the workers. The objective of this study is to assess a radiation dose for workers transporting spent nuclear fuel using metal overpacks. For this objective, the cask to be handled was selected and the radiation source term was set. Then, the radiation exposure scenario for the transportation workers was defined. Finally, the dose rates for each location of operation were assessed using Monte Carlo simulations, and collective doses were derived for each operation considering the radiation exposure scenario. Each worker performed 11 operations to transport spent nuclear fuel to other facilities and was exposed to a total of 1.138 man-mSv. The operation of removing the bottom shield ring resulted in the highest radiation exposure at 0.503 man-mSv. In contrast, the operation of installing the impact limiter resulted in the lowest radiation exposure at 0.0009 man-mSv. The results of this study can be used to strengthen radiation protection measures for workers transporting spent nuclear fuel in dry storage facilities using metal overpacks.
2. Materials and Methods
2.1 Cask for Assessment and RadiationSource Term
2.2 Radiation Exposure Scenario for WorkersTransporting Spent Nuclear Fuel
2.3 Occupational Radiation Dose to WorkersTransporting Spent Nuclear Fuel
3. Results and Discussions
3.1 Radiation Dose Rate at Locations of Operation
3.2 Radiation Dose for Workers TransportingSpent Nuclear Fuel Using Metal Overpack
4. Conclusion
Conflict of Interest
Acknowledgements
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