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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2018.1
- 수록면
- 1,289 - 1,297 (9page)
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Preliminary surface soil Derived Concentration Guideline Levels (DCGLs) were derived conforming to theMulti-Agency Radiation Site Survey and Investigation Manual (MARSSIM) procedure for the site releaseand reuse of Kori Unit 1 in Korea. Based on the decommissioning experiences of the U.S. nuclear powerplants, a suite of residual radionuclides was determined, and uncertainties contributed to the resultantdose by the input parameters were quantified via the sensitivity analysis of parameters. The peak of themean dose was obtained via the probabilistic analysis of the RESRAD (RESidual RADioactivity)-ONSITEcode. Consequently, DCGLw of Kori Unit 1 in accordance with two scenarios, industrial worker andresidential farmer scenario, were derived and the results were compared respectively with other NPPs. Itcould be used as a basic guideline for establishing regulatory standards for reuse planning, designing thesite characterization surveys and implementing final status survey (FSS).
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참고문헌 (24)
참고문헌 신청
U.S. Nuclear Regulatory Commission / 2006 / Consolidated Decommissioning Guidance e Characterization, Survey, and Determination of Radiological Criteria
U.S. Nuclear Regulatory Commission / 1984 / Long-lived Activation Products in Reactor Materials
U.S. Nuclear Regulatory Commission / 1986 / Residual Radionuclide Contamination within and Around Commercial Nuclear Power Plants
U.S. Nuclear Regulatory Commission / 1986 / Technology, Safety, and Costs of Decommissioning a Reference Pressurized Water Reactor Power Station
National Council on Radiation Protection and Measurement / 1984 / A Handbook of Radioactivity Measurements Procedures
U.S. Nuclear Regulatory Commission / 1984 / Long-lived Activation Products in Reactor Materials
U.S. Nuclear Regulatory Commission / 1986 / Residual Radionuclide Contamination within and Around Commercial Nuclear Power Plants
U.S. Nuclear Regulatory Commission / 1986 / Technology, Safety, and Costs of Decommissioning a Reference Pressurized Water Reactor Power Station
National Council on Radiation Protection and Measurement / 1984 / A Handbook of Radioactivity Measurements Procedures
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Derivation of Preliminary Derived Concentration Guideline Level (DCGL) by Containment Building Reuse Scenario for Kori Unit 1 Using RESRAD-BUILD
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Derivation of DCGLs for the Surface Soil of Kori-1 NPP by Using RESRAD Probabilistic Analysis
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Derivation and Comparison of Preliminary Derivation Concentration Guideline Level (DCGL) According to Scenarios of Kori Unit 1 Using RESRAD-BUILD
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A study on the dose evaluation of critical groups for unrestricted reuse of the site after the decommissioning of Kori Unit 1
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Derivation of Surface Soil DCGL for Kori-1 NPP Reuse Scenario
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Derivation of preliminary derived concentration guideline level (DCGL) by reuse scenario for Kori Unit 1 using RESRAD-BUILD
Nuclear Engineering and Technology
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Derivation of Surface Soil Area Factor for Kori-1 NPP by Using RESRAD-ONSITE
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2018 .01
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Status of Development of Final Decommissioning Plan for Kori Unit 1
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Calculation of Preliminary Site-Specific DCGLs for Nuclear Power Plant Decommissioning Using Hybrid Scenarios
Nuclear Engineering and Technology
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원자력발전소 해체 부지의 방사성오염 분포에 따른 조사설계 오차한계 분석
방사선산업학회지
2022 .06
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A Methodology of Selecting Potential Radionuclides for the Kori Unit 1 DCGL Calculation
한국방사성폐기물학회 학술대회
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Study on Dismantling Scenario for Large Components of Kori Unit 1
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2018 .01
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Proposal for the list of potential radionuclides of interest during NPP site characterization or fi nal status surveys
Nuclear Engineering and Technology
2021 .01
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Proposal of Decommissioning Planning for Kori Site
한국방사성폐기물학회 학술대회
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External exposure specific analysis for radiation worker in reuse of containment building for Kori Unit 1
Nuclear Engineering and Technology
2022 .05
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Simulation-Based Evaluation for the Dismantling Scenario of the Reactor Vessel at Kori Unit 1
한국방사성폐기물학회 학술대회
2017 .01
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Kori-1 Decommissioning Project Expense Evaluation
한국방사성폐기물학회 학술대회
2018 .01
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Suggestion of Kori-1 Decommissioning Target Facilities
한국방사성폐기물학회 학술대회
2018 .01
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Radiation Shielding Evaluation for Existing Transport Container Containing Decommissioning Waste of KORI Unit 1
한국방사성폐기물학회 학술대회
2019 .01
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A Study on the Development of Interview Procedure for HSA at Kori Unit 1
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