Radiological safety assessment for incident-free transportation of radioactive decontamination waste after the Fukushima nuclear power plant accident
Radioactive decontamination waste generated by remediation following the Fukushima nuclear power plant accident was recently transported from its temporary storage sites to interim storage facilities as a pilot test. A transportation plan for the radioactive decontamination waste will be developed b...
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| Format: | Article |
| Language: | English |
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VINCA Institute of Nuclear Sciences
2019-01-01
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| Series: | Nuclear Technology and Radiation Protection |
| Subjects: | |
| Online Access: | http://www.doiserbia.nb.rs/img/doi/1451-3994/2019/1451-39941900011K.pdf |
| _version_ | 1818129392401907712 |
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| author | Kim Min Jun Song Ji Young Park Jin Ho Do Tae Gwan Lee Jin O. Kim Kwang Pyo |
| author_facet | Kim Min Jun Song Ji Young Park Jin Ho Do Tae Gwan Lee Jin O. Kim Kwang Pyo |
| author_sort | Kim Min Jun |
| collection | DOAJ |
| description | Radioactive decontamination waste generated by remediation following the Fukushima nuclear power plant accident was recently transported from its temporary storage sites to interim storage facilities as a pilot test. A transportation plan for the radioactive decontamination waste will be developed based on this pilot transportation experience and radiological safety assessment of pilot transportation. The objective of this study was to assess radiation doses to the public and crew workers released during incident-free pilot transportation. External dose rates around a transportation vehicle were calculated by using the Monte Carlo N-Particle code. Collective doses and maximally exposed individual doses to the public and effective doses to crew workers were calculated by using INTERTRAN. Two transportation routes, Asakawa-machi to Okuma-machi and Iwaki-shi to Okuma-machi, were considered. The maximum radioactivity concentration in the decontamination waste was calculated to be 660 kBqkg–1 which meets the value laid down by the guidelines of Japan's Ministry of the Environment. The collective doses to the public per shipment were 1.9 10–3 person-mSv for the Asakawa route and 2.2 10–4 person-mSv for the Iwaki route. Maximally exposed individual doses to the public were 9.6 10–7 mSv for the Asakawa route and 2.7 10–5 mSv for the Iwaki route. The total effective doses to crew workers were 0.27 mSv for the Asakawa route assuming five shipments per worker and 1.07 mSv for the Iwaki route assuming 45 shipments per worker. The radiation dose levels to the public and workers evaluated in this study were much lower than the annual dose limits for the general public and radiation workers. These study results can be used to develop transportation plans and guidelines for decontamination waste transportation. |
| first_indexed | 2024-12-11T07:48:25Z |
| format | Article |
| id | doaj.art-9ef3468def854375b677548462484526 |
| institution | Directory Open Access Journal |
| issn | 1451-3994 1452-8185 |
| language | English |
| last_indexed | 2024-12-11T07:48:25Z |
| publishDate | 2019-01-01 |
| publisher | VINCA Institute of Nuclear Sciences |
| record_format | Article |
| series | Nuclear Technology and Radiation Protection |
| spelling | doaj.art-9ef3468def854375b6775484624845262022-12-22T01:15:24ZengVINCA Institute of Nuclear SciencesNuclear Technology and Radiation Protection1451-39941452-81852019-01-0134220120810.2298/NTRP181015011K1451-39941900011KRadiological safety assessment for incident-free transportation of radioactive decontamination waste after the Fukushima nuclear power plant accidentKim Min Jun0Song Ji Young1Park Jin Ho2Do Tae Gwan3Lee Jin O.4Kim Kwang Pyo5Kyung Hee University, Department of Nuclear Engineering, Yongin, Gyeonggi-do, Republic of KoreaKyung Hee University, Department of Nuclear Engineering, Yongin, Gyeonggi-do, Republic of KoreaKyung Hee University, Department of Nuclear Engineering, Yongin, Gyeonggi-do, Republic of KoreaKyung Hee University, Department of Nuclear Engineering, Yongin, Gyeonggi-do, Republic of KoreaKyung Hee University, Department of Nuclear Engineering, Yongin, Gyeonggi-do, Republic of KoreaKyung Hee University, Department of Nuclear Engineering, Yongin, Gyeonggi-do, Republic of KoreaRadioactive decontamination waste generated by remediation following the Fukushima nuclear power plant accident was recently transported from its temporary storage sites to interim storage facilities as a pilot test. A transportation plan for the radioactive decontamination waste will be developed based on this pilot transportation experience and radiological safety assessment of pilot transportation. The objective of this study was to assess radiation doses to the public and crew workers released during incident-free pilot transportation. External dose rates around a transportation vehicle were calculated by using the Monte Carlo N-Particle code. Collective doses and maximally exposed individual doses to the public and effective doses to crew workers were calculated by using INTERTRAN. Two transportation routes, Asakawa-machi to Okuma-machi and Iwaki-shi to Okuma-machi, were considered. The maximum radioactivity concentration in the decontamination waste was calculated to be 660 kBqkg–1 which meets the value laid down by the guidelines of Japan's Ministry of the Environment. The collective doses to the public per shipment were 1.9 10–3 person-mSv for the Asakawa route and 2.2 10–4 person-mSv for the Iwaki route. Maximally exposed individual doses to the public were 9.6 10–7 mSv for the Asakawa route and 2.7 10–5 mSv for the Iwaki route. The total effective doses to crew workers were 0.27 mSv for the Asakawa route assuming five shipments per worker and 1.07 mSv for the Iwaki route assuming 45 shipments per worker. The radiation dose levels to the public and workers evaluated in this study were much lower than the annual dose limits for the general public and radiation workers. These study results can be used to develop transportation plans and guidelines for decontamination waste transportation.http://www.doiserbia.nb.rs/img/doi/1451-3994/2019/1451-39941900011K.pdffukushima nuclear power plant accident accidentdecontamination wasteinterim storage facilitytransportationsafety assessment |
| spellingShingle | Kim Min Jun Song Ji Young Park Jin Ho Do Tae Gwan Lee Jin O. Kim Kwang Pyo Radiological safety assessment for incident-free transportation of radioactive decontamination waste after the Fukushima nuclear power plant accident Nuclear Technology and Radiation Protection fukushima nuclear power plant accident accident decontamination waste interim storage facility transportation safety assessment |
| title | Radiological safety assessment for incident-free transportation of radioactive decontamination waste after the Fukushima nuclear power plant accident |
| title_full | Radiological safety assessment for incident-free transportation of radioactive decontamination waste after the Fukushima nuclear power plant accident |
| title_fullStr | Radiological safety assessment for incident-free transportation of radioactive decontamination waste after the Fukushima nuclear power plant accident |
| title_full_unstemmed | Radiological safety assessment for incident-free transportation of radioactive decontamination waste after the Fukushima nuclear power plant accident |
| title_short | Radiological safety assessment for incident-free transportation of radioactive decontamination waste after the Fukushima nuclear power plant accident |
| title_sort | radiological safety assessment for incident free transportation of radioactive decontamination waste after the fukushima nuclear power plant accident |
| topic | fukushima nuclear power plant accident accident decontamination waste interim storage facility transportation safety assessment |
| url | http://www.doiserbia.nb.rs/img/doi/1451-3994/2019/1451-39941900011K.pdf |
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