Radiological Safety Assessment of Transporting Radioactive Wastes to the Gyeongju Disposal Facility in Korea

Jeong, Jongtae; Baik, Min Hoon; Kang, Mun Ja; Ahn, Hong-Joo; Hwang, Doo-Seong; Hong, Dae-Seok; Jeong, Yong-Jin; Kim, Kyungsu

doi:10.1016/j.net.2016.05.003

Cited by 15 publications

(6 citation statements)

References 1 publication

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“…The radionuclide release fraction due to containment failure is conservatively set at 0.1% [28][29][30]. The 0.1% radionuclide release fraction is recommended as an upper bound for preliminary assessments [11,29]. The aerosol fraction is the fraction of the released radionuclide that is aerosolized.…”

Section: Transportation Accident Scenariosmentioning

confidence: 99%

“…Unfortunately, there is a limitation in this study. When assessing the radiological risk and dose from transporting radioactive waste under accident conditions, the most important parameter is the release fraction of each radionuclide [11]. The release fraction varies with the physical/chemical properties of each radionuclide and the severity of the accident [21].…”

Section: Doses and Radiological Risks Under Normal Operation Scenariosmentioning

confidence: 99%

“…The Danish National Board of Health (NHB) conducted a radiological safety assessment of the decommissioning waste from the Risoe Research Reactor using the RADTRAN code [9]. The Korea Atomic Energy Research Institute (KAERI) identified the decommissioning wastes and transport vehicles for Korea Research Reactor Unit 1&2 and conducted radiological safety assessments for transportation to the Gyeongju disposal facility [10,11]. The Nuclear Regulatory Commission (NRC) conducted a radiological safety assessment for the transportation of radioactive waste, reflecting the characteristics of many NPPs [12].…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Radiological safety assessment for transportation of reactor pressure vessel during decommissioning of a nuclear power plant in Korea

Kwak,

Kim,

et al. 2024

J. Radiol. Prot.

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In Korea, decommissioning of NPPs and transportation of the decommissioning waste are expected to expand in the near future. It is necessary to confirm that radiological risks to the public and workers are not significant through radiological safety assessment. The objective of this study is to assess the radiological safety for transportation of RPV waste, which is a major decommissioning waste with relatively high level of radioactivity. It was assumed that the waste would be tranported to the Gyeongju disposal facility by land transportation. First, the source term and transportation method of the RPV waste were determined, and the external dose rates from the waste were calculated using MCNP. Then, transportation scenarios were assumed under both normal and accident conditions. Under the scenarios, radiation doses were calculated using the RADTRAN. Under normal operation scenarios without a transportation accident, assuming 40 shipments per year, the average individual doses for the public ranged from 6.56×10-6 to 2.18×10-2 mSv yr-1. The maximum invidual doses for only a single shipment ranged from 2.43×10-6 to 3.14×10-1 mSv. For cargo handlers and vehicle crew members, the average doses were 2.26×101 mSv yr-1 and 2.95 mSv yr-1, respectively. Under transportation accident scenarios, average individual radiological risks which are product of the radiation doses and the annual accident rates ranged from 1.14×10-11 to 1.61×10-10 mSv yr-1 by transportation route segment when considering the transportation accident rate. Average individual doses assuming transportation accident occurrence ranged from 2.62×10-4 to 1.42×10-3 mSv. The maximum individual dose under accident conditions was 7.99×10-2 mSv. The calculated doses were below the regulatory limits in Korea. However, relatively high doses were observed for cargo handlers and vehicle crew members because of conservative assumptions. This study results can be used as basic data for the radiological safety assessment for the decommissioning waste transportation in the future.

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Section: Transportation Accident Scenariosmentioning

confidence: 99%

Section: Doses and Radiological Risks Under Normal Operation Scenariosmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Radiological safety assessment for transportation of reactor pressure vessel during decommissioning of a nuclear power plant in Korea

Kwak,

Kim,

et al. 2024

J. Radiol. Prot.

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“…Keseluruhan kegiatan ini artinya dikategorikan sebagai pengangkutan normal. Pengangkutan Normal (incident-free) adalah pengangkutan yang tidak terdapat kejadian kecelakaan, kelainan pengemasan atau penanganan, dan serangan jahat [2]. Selama pengangkutan berjalan normal, wadah tidak rusak, dan potensi paparan yang dipertimbangkan adalah paparan eksternal [3].…”

Section: Hasil Dan Pembahasanunclassified

Kajian Dosis Pengangkutan Zat Radioaktif Sebagai Upaya Penetapan Program Pengangkutan di PRTRR

Bisma Barron Patrianesha,

Didik Setiaji,

Fath Priyadi

et al. 2023

Prosiding Seminar Nasional Aplikasi Isotop Dan Radiasi 2021: Peran Isotop Dan Radiasi Untuk Indonesia Yang Berdaya Saing

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Telah dilakukan sebuah kajian dosis pada kegiatan pengangkutan zat radioaktif di Pusat Riset dan Teknologi Radioisotop dan Radiofarmaka (PRTRR), Serpong, Indonesia. Zat radioaktif yang diangkut adalah zat radioaktif yang diproduksi oleh PRTRR berbentuk radiofarmaka yang digunakan di rumah sakit. Bagian terpenting dari kajian dosis ini adalah data radiologi pada pengangkutan normal (incident-free) radiofarmaka. Data radiologi tersebut adalah paparan radiasi pada personel pengangkut dan pekerja yang melakukan bongkar-muat bungkusan. Parameter yang digunakan dalam melakukan kajian dosis ini adalah jumlah dan tipe bungkusan, kategori bungkusan dan Indeks Angkut, zat radioaktif yang dikirim, frekuensi pengiriman, durasi penyimpanan dan pengangkutan, laju dosis bungkusan, waktu paparan, jarak/pemisahan, dan pengaturan shielding. Data-data pengangkutan yang digunakan untuk menghitung dosis efektif berdasarkan parameter kajian dosis adalah data pengangkutan selama tahun 2020. Berdasarkan data-data tersebut didapatkan dosis efektif bagi petugas pengangkut dan petugas bongkar muat selama tahun 2020 adalah 0,047 mSv. Nilai ini masih jauh di bawah 20 mSv per tahun yang merupakan batas yang ditetapkan oleh Badan Pengawas Tenaga Nuklir (BAPETEN). Dengan dosis efektif sebesar 0,047 mSv, pengangkutan zat radioaktif di PRTRR tidak diwajibkan untuk melakukan pemantauan dosis personel dan/atau pemantauan daerah kerja. Hal ini disebabkan karena kewajiban pengirim dalam melakukan pemantauan dosis perorangan dan/atau pemantauan paparan daerah kerja pada dosis efektif di bawah 1 mSv tidak diatur secara jelas dalam Peraturan Kepala BAPETEN No. 7 Tahun 2020. Hasil kajian ini dapat dijadikan panduan untuk membuat program proteksi dan keselamatan radiasi khusus kegiatan transportasi sebagai manual untuk melaksanakan kegiatan pengangkutan zat radioaktif.

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“…The waste from TRIGA 2000 research reactor can be stored temporarily at the installation site and can also be in a permanent waste storage area outside the site. When the second option is decided, using a permanent waste facility in Serpong nuclear area, the process of transferring the waste from the site to a permanent storage area will involve additional aspects, such as the safety aspect of transportation of radioactive waste materials [14].…”

Section: Safety Assessment Frameworkmentioning

confidence: 99%

Risk Assessment on the Decommissioning Stage of Indonesian Triga 2000 Research Reactor

Tyas

Deswandri²,

Intaningrum³

et al. 2022

Tri Dasa Mega

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Decommissioning is the final stage of a nuclear reactor. In preparing the decommissioning plan, one of the important elements that need to be considered is safety assessment. During decommissioning, there are many complex tasks to be done where the radiological and non-radiological hazards arise and can significantly affect not only the workers but also the general public and the environment. Indonesia has no experience with nuclear reactor decommissioning, so it is necessary to study various experiences of decommissioning activities in the world. This study proposes a framework to implement the safety assessment on the decommissioning of the TRIGA 2000 research reactor. The framework was developed on desk-based research and analysis. The proposed framework involves the facility and decommissioning activities, hazard identification, hazard analysis, hazard evaluation, hazard or risk control, and independent review.

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Radiological Safety Assessment of Transporting Radioactive Wastes to the Gyeongju Disposal Facility in Korea

Cited by 15 publications

References 1 publication

Radiological safety assessment for transportation of reactor pressure vessel during decommissioning of a nuclear power plant in Korea

Radiological safety assessment for transportation of reactor pressure vessel during decommissioning of a nuclear power plant in Korea

Kajian Dosis Pengangkutan Zat Radioaktif Sebagai Upaya Penetapan Program Pengangkutan di PRTRR

Risk Assessment on the Decommissioning Stage of Indonesian Triga 2000 Research Reactor

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