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Contents

Safety assessment for the landfill disposal of decommissioning waste solidified by magnesium potassium phosphate cement / Jongtae Jeong ; Min-Hoon Baik ; Jae-Kwang Lee ; Jae-Young Pyo ; Wooyong Um ; Jong Heo 1

[요약] 1

1. Introduction 2

2. Materials and Methods 3

2.1. Solidified Concrete Waste 3

2.2. RESRAD-ONSITE Code 5

2.3. Input Variables and Scenarios 5

3. Results and Discussion 6

3.1. Estimation of Exposure Doses 6

3.2. Exposure Doses for Scenarios 6

3.3. Sensitivity Analyses of the Input Parameters of the Cover 8

4. Conclusions 9

REFERENCES 10

초록보기

The decommissioning of a nuclear power plant generates large amounts of radioactive waste, which is of several types. Radioactive concrete powder is classified as low-level waste, which can be disposed of in a landfill. However, its safe disposal in a landfill requires that it be immobilized by solidification using cement. Herein, a safety assessment on the disposal of solidified radioactive concrete powder waste in a conceptual landfill site is performed using RESRAD. Furthermore, sensitivity analyses of certain selected input parameters are conducted to investigate their impact on exposure doses. The exposure doses are estimated, and the relative impact of each pathway on them during the disposal of this waste is assessed. The results of this study can be used to obtain information for designing a landfill site for the safe disposal of low-level radioactive waste generated from the decommissioning of a nuclear power plant.

The decommissioning of a nuclear power plant generates large amounts of radioactive waste, which is of several types. Radioactive concrete powder is classified as low-level waste, which can be disposed of in a landfill. However, its safe disposal in a landfill requires that it be immobilized by solidification using cement. Herein, a safety assessment on the disposal of solidified radioactive concrete powder waste in a conceptual landfill site is performed using RESRAD. Furthermore, sensitivity analyses of certain selected input parameters are conducted to investigate their impact on exposure doses. The exposure doses are estimated, and the relative impact of each pathway on them during the disposal of this waste is assessed. The results of this study can be used to obtain information for designing a landfill site for the safe disposal of low-level radioactive waste generated from the decommissioning of a nuclear power plant.

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기사명 저자명 페이지 원문 목차
Surface modification of bentonite for the improvement of radionuclide sorption Seokju Hong, Jueun Kim, Wooyong Um p. 1-12

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Safety assessment for the landfill disposal of decommissioning waste solidified by magnesium potassium phosphate cement Jongtae Jeong, Min-Hoon Baik, Jae-Kwang Lee, Jae-Young Pyo, Wooyong Um, Jong Heo p. 13-22

보기
Estimation of input material accounting uncertainty with double-stage homogenization in pyroprocessing Chaehun Lee, Bong Young Kim, Byung-Hee Won, Hee Seo, Se-Hwan Park p. 23-32

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Electrochemical behaviors of Bi3+ ions on inert tungsten or on liquid Bi pool in the molten LiCl-KCl eutectic Beom Kyu Kim, Byung Gi Park p. 33-41

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Corrosion of containment alloys in molten salt reactors and the prospect of online monitoring Thomas Hartmann, Patricia Paviet p. 43-63

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UK civil nuclear decommissioning, a blueprint for Korea’s nuclear decommissioning future?. pt. 2, UK’s progress and implications for Korea Richard I. Foster, June Kyung Park, Keunyoung Lee, Bum-Kyoung Seo p. 65-98

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Development of micro-blast type scabbling technology for contaminated concrete structure in nuclear power plant decommissioning Kyungho Lee, Sewon Chung, Kihyun Park, SeongHee Park p. 99-110

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What are technical hurdles of verification for North Korea’s nuclear program Sungyeol Choi, Eunju Jun p. 111-118

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Code requirements for fuel handling equipment at nuclear power plant Sang-Gyoon Chang, Tae-Kyo Kang, Jong-Min Kim, Jong-Pil Jung p. 119-126

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(An) approach to the localization of technology for a transport and storage container for very low-level radioactive liquid waste Seung Hun Shin, Woo Nyun Choi, Seungbin Yoon, Un Jang Lee, Hye Min Park, Hee Reyoung Kim p. 127-131

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참고문헌 (11건) : 자료제공( 네이버학술정보 )

참고문헌 목록에 대한 테이블로 번호, 참고문헌, 국회도서관 소장유무로 구성되어 있습니다.
번호 참고문헌 국회도서관 소장유무
1 Nuclear Safety and Security Commission, A Draft Permission for the Operation Change of Kori Unit 1 Nuclear Power Plant, NSSC Press Release (2017). 미소장
2 International Atomic Energy Agency. Managing Low Radioactivity Material From the Decommissioning of Nuclear Facilities, IAEA Report, Technical Reports Series No. 462 (2008). 미소장
3 Nuclear Safety and Security Committee, The Regulation on the Classification of Radioactive Wastes and Regulatory Clearance, NSSC Notice No. 2020-6 (2020). 미소장
4 J.Y. Pyo, W. Um, and J. Heo, “Magnesium Potassium Phosphate Cements to Immobilize Radioactive Concrete Wastes Generated by Decommissioning of Nuclear Power Plants”, Nucl. Eng. Technol., 53(7), 2261-2267 (2021). 미소장
5 Radioactivity. “An Operational Repository for Very low-level Waste.” Radioactivity. Accessed Aug. 102021. Available from: http://radioactivity.eu.com/site/pages/VLLW_Disposal.htm. 미소장
6 S. Kamboj, E. Gnanapragasam, and C. Yu. User’s Guide for RESRAD-ONSITE Code, Version 7.2, Argonne National Laboratory Technical Report, ANL/EVS/TM-18/1 (2018). 미소장
7 C. Yu, A.J. Zielen, J.J. Cheng, D.J. LePoire, E. Gnanapragasam, A. Wallo, W.A. Williams, and H. Peterson. User’s Manual for RESRAD Version 6, Argonne National Laboratory Technical Report, ANL/EAD-4 (2001). 미소장
8 W.S. Jeong, S.B. Hong, B.K. Seo, S.K. Park, and J.H. Park, “Safety Assessment for the Disposal of Very Low-Level Radioactive Concreter Wastes”, Proc. of the 2003Autumn Meeting, Korean Nuclear Society, Yongpyong (2003). 미소장
9 J. Jeong, N.Y. Ko, D.K. Cho, M.H. Baik, and K.H. Yoon, “Estimation of Exposure Doses for the Safe Management of NORM Waste Disposal”, Radiat. Prot. Dosimetry, 181(4), 394-402 (2018). 미소장
10 J. Jang, T.M. Kim, C.H. Cho, and D.S. Lee, “Radiological Safety Assessment for a Near-Surface Disposal Facility Using RESRAD-ONSITE Code”, J. Nucl. Fuel Cycle Waste Technol., 19(1), 123-132 (2021). 미소장
11 International Commission on Radiation Protection, “Age-dependent Doses to Members of the Public From Intake of Radionuclides: Part 5 Compilation of Ingestion and Inhalation Dose Coefficient”, Ann. ICRP, 26(1), 1-91 (1996). 미소장

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