The Assessment and Reduction Plan of Radiation Exposure During Decommissioning of the Steam Generator in Kori Unit 1

Son, Young Jik; Park, Sang June; Byon, Jihyang; Ahn, Seokyoung

doi:10.7733/jnfcwt.2018.16.3.377

Cited by 5 publications

(17 citation statements)

References 3 publications

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“…The decommissioning plan consists of 11 chapters, and safety assessment provides in Chapter 6 [6]. Chapter 6 is organized by 6 subsections: (1) principles and standards, (2) scenario, (3) assessment of exposure, (4) residual radioactivity, (5) abnormal events, and (6) risk assessment, which provide radiation effect to the worker, resident, and environment. Especially, there would be a concern about the radiation impact on workers, because decommissioning spent more than 10 years before it was remedial or re-used in contaminated sites.…”

Section: Jrprmentioning

confidence: 99%

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An External Dose Assessment of Worker during RadWaste Treatment Facility Decommissioning

Chae

Park²,

Park³

et al. 2020

J Radiat Prot Res

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Background: Kori unit #1 is permanently shut down after a 40-year lifetime. The Nuclear Safety and Security Commission recommends establishing initial decommissioning plans for all nuclear and radwaste treatment facilities. Therefore, the Korea Atomic Energy Research Institute (KAERI) must establish an initial and final decommissioning plan for radwaste-treatment facilities. Radiation safety assessment, which constitutes one chapter of the decommissioning plan, is important for establishing a decommissioning schedule, a strategy, and cost. It is also a critical issue for the government and public to understand. Materials and Methods: This study provides a method for assessing external radiation dose to workers during decommissioning. An external dose is calculated following each exposure scenario, decommissioning strategy, and working schedule. In this study, exposure dose is evaluated using the deterministic method. Physical characterization of the facility is obtained by both direct measurement and analysis of the drawings, and radiological characterization is analyzed using the annual report of KAERI, which measures the ambient dose every month. Results and Discussion: External doses are calculated at each stage of a decommissioning strategy and found to increase with each successive stage. The maximum external dose was evaluated to be 397.06 man-mSv when working in liquid-waste storage. To satisfy the regulations, working period and manpower must be managed. In this study, average and cumulative exposure doses were calculated for three cases, and the average exposure dose was found to be about 17 mSv/yr in all the cases. Conclusion: For the three cases presented, the average exposure dose is well below the annual maximum effective dose restriction imposed by the international and domestic regulations. Working period and manpower greatly affect the cost and entire decommissioning plan; hence, the chosen option must take account of these factors with due consideration of worker safety.

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Section: Jrprmentioning

confidence: 99%

“…The nuclear industry of Korea begins the decommissioning stage. Not only nuclear power plant (NPP) but also an institution that has a nuclear fuel cycle facility prepare the initial and final decommissioning plan [1][2][3][4][5].…”

Section: Introductionmentioning

confidence: 99%

An External Dose Assessment of Worker during RadWaste Treatment Facility Decommissioning

Chae

Park²,

Park³

et al. 2020

J Radiat Prot Res

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“…It is noted that only the potential radiological impact from scenarios representing normal conditions in the processing and transportation of SGs have been considered in this comparative study, whereas off-normal or accidental scenarios with low probabilities are subject to preparedness and responses to emergencies [13,14].…”

Section: Basic Equations To Calculate Radiation Dosementioning

confidence: 99%

“…In this section, a set of general pathway dose factors (PDFs) was derived for each radionuclide at its unit activity concentration based upon the processing and transportation of a reference SG of the Optimized Power Reactor (OPR 1000) with a weight of 540 tons and reported physical dimensions of 21 m in height and 5.7 m in outer diameter [25,26]. In total, 26 radionuclides are referenced from publicly available inventory data for SGs from a PWR (Kori Unit 1) and a PHWR (Bruce A Unit 1) and considered in the general assessment [14,27]: eight actinides ( 237 Np, 238 Pu, 239 Pu, 240 Pu, 241 Am, 242 Pu, 243 Am, and 244 Cm), six fission products ( 90 Sr, 99 Tc, 106 Ru, 129 I, 137 Cs, and 144 Ce), 10 activated corrosion products ( 54 Mn, 55 Fe, 57 Co, 59 Ni, 60 Co, 63 Ni, 65 Zn, 94 Nb, 125 Sb, and 154 Eu), and two others ( 3 H and 14 C).…”

Section: General Assessment For the Predisposal Management Of Dismant...mentioning

confidence: 99%

“…However, no comprehensive studies have been reported on the radiological risk assessments for all possible predisposal management options of large components in an integrated manner. For instance, a preliminary study has estimated the radiation doses for the decommissioning workers involved in the cutting and smelting of an SG, with neither assessment of the handling of the SG in one piece nor its transportation to offsite [14]. Other studies on radiological risk assessment for the transportation-but not the processing-of two actual SGs from German NPPs to offsite facilities have been conducted, such as (a) the overseas transport of four SGs from Stade NPP to Studsvik processing plant in Sweden and (b) the transport of SGs in one piece from Obrigheim NPP to the Lubmin offsite interim storage facility through road and inland waterways [13].…”

Section: Introductionmentioning

confidence: 99%

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Calculation of Potential Radiation Doses Associated with Predisposal Management of Dismantled Steam Generators from Nuclear Power Plants

2020

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Although the generation of large components from nuclear power plants is expected to gradually increase in the future, comprehensive studies on the radiological risks of the predisposal management of large components have been rarely reported in open literature. With a view to generalizing the assessment framework for the radiological risks of the processing and transport of a representative large component—a steam generator—12 scenarios were modeled in this study based on past experiences and practices. In addition, the general pathway dose factors normalized to the unit activity concentration of radionuclides for processing and transportation were derived. Using the general pathway dose factors, as derived using the approach established in this study, a specific assessment was conducted for steam generators from a pressurized water reactor (PWR) or a pressurized heavy water reactor (PHWR) in Korea. In order to demonstrate the applicability of the developed approach, radiation doses reported from actual experiences and studies are compared to the calculated values in this study. The applicability of special arrangement transportation of steam generators assumed in this study is evaluated in accordance with international guidance. The generalized approach to assessing the radiation doses can be used to support optimizing the predisposal management of large components in terms of radiological risk.

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A multi-criteria decision-making process for selecting decontamination methods for radioactively contaminated metal components

Hahm

Kim

Ryu

et al. 2023

Nuclear Engineering and Technology

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The Assessment and Reduction Plan of Radiation Exposure During Decommissioning of the Steam Generator in Kori Unit 1

Cited by 5 publications

References 3 publications

An External Dose Assessment of Worker during RadWaste Treatment Facility Decommissioning

An External Dose Assessment of Worker during RadWaste Treatment Facility Decommissioning

Calculation of Potential Radiation Doses Associated with Predisposal Management of Dismantled Steam Generators from Nuclear Power Plants

A multi-criteria decision-making process for selecting decontamination methods for radioactively contaminated metal components

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