과제정보
본 논문은 에너지기술평가원(KETEP)에서 주관하는 원자력핵심기술개발 "방사성폐기물 종류별 물리적 특성 규명을 통한 처분시설 폐쇄 후 안전성 평가 체계 고도화" 과제(과제번호 : RS-2023-00235182)의 일환으로 수행되었습니다.
참고문헌
- Sohn H-D, Park K-S, Kim H-W, Kim C-W, Hwang Y-H and Yoon J-Y. 2020. The study for activation evaluation on activated structures in nuclear power plant with 40 years operation history. Annals of Nuclear Energy 141:107305. https://doi.org/10.1016/j.anucene.2020.107305.
- Dho H-S, Kang H-G, Cho Y-S, Cho C-H. 2022. Annual report of Development of Waste Package, Transportation and Disposal Containers for Decommissioning Wastes of Nuclear Power Plant. Korea Radioactive Waste Agency report. RND-K-TR-003.
- Park J, Yang W, Chae N, Lee M and Choi S. 2020. Internal Dose Assessment of Worker by Radioactive Aerosol Generated During Mechanical Cutting of Radioactive Concrete. JNFCWT 18(2):157-167. https://doi.org/10.7733/jnfcwt.2023.031.
- Kang G-W, Kim R-A, Do H-S, Kim T-M and Cho C-H. 2021. A study on the evaluation of surface dose rate of new disposal containers though the activation evaluation of bio-shield concrete waste from kori unit 1. JNFCWT 19(1):133-140. https://doi.org/10.7733/jnfcwt.2021.19.1.133.
- Evans JC, Lepel EL, Sanders RW, Wilker CL, Silker W, Thomas CW, Abel KH and Robertson DR. 1984. Long-lived activation products in reactor materials. Pacific Northwest Laboratory Report, 85-89, NUREG/CR-3474.
- International Atomic Energy Agency. 2011. Disposal of Radioactive Waste", No. SSR-5.
- International Atomic Energy Agency. 2012. The safety case and safety assessment for the disposal of radioactive waste, No. SSG-23.
- Korea Radioactive Waste Agency. 2014. The safety case program for disposal facility.
- Lloyd RL. 2001. Technical Assessment Generic Issue 186: Potential Risk and Consequences of Heavy Load Drops in Nuclear Power Plants. Pre-draft NUREG-XXXX (ML012620352). Washington, DC: U.S. Nuclear Regulatory Commission. ACC: MOL.20011107.0009.
- Oztunali OI and Roles GW. 1986. Update of Part 61 Impact Analysis Methodology. U.S. Nuclear Regulatory, Vol.1, NUREG/CR-4370.
- Anigstein R, Chmelynski HJ, Loomis DA, Marschke SF, Mauro JJ, Olsher RH, Thurber WC and Meek RA. 2003. Radiological assessments for clearance of materials from nuclear facilities, U.S. Nuclear Regulatory Commission Report, NUREG-1640.
- ASME Boiler & Pressure Vessel Code. 2015. Materials-Property (Metric), ASME Section II.
- Los Alamos National Laboratory. 2013. MCNP6 Users Manual - Code Version 1.0, 15-40, LA-CP-13-00634.
- International Commission on Radiological Protection. 1997. Conversion coefficients for use in radiological protection against external radiation. ICRP Publication 74. Pergamon Press, Oxford, UK.
- U.S. Department Of Energy. 2006. Waste Isolation Pilot Plant Contact Handled Waste Documented Safety Analysis. DOE/WIPP-95-2065.
- U.S. Department Of Energy. 2013. Airborne Release Fractions Rates and Respirable Fraction for Non-reactor Nuclear Facilities. DOE/HDBK-3010-94.
- U.S. NRC. 1974. Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors, Regulatory Guide 1.4.
- International Commission on Radiological Protection. 1997. Age dependent dose to members of the public from intake of radionuclides; Part5 compilation of ingestion and inhalation dose coefficients, ICRP publication 72, Pergamon Press, Oxford, UK.
- U.S. Department Of Energy. 1988. External Dose rate Conversion Factors for Calculation of Dose to the Public. DOE/EH-0070.