The effect of sensitive and non-sensitive parameters on DCGL in probability analysis for decommissioning of nuclear facilities
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In the decommissioning of nuclear facilities, Derived Concentration Guideline Level (DCGL) derivation is necessary for the release of the facility after the site remediation, which also needs to be implemented in the stage of establishing a decommissioning planning. In order to derive DCGL, the dose assessment for the receptors can be conducted from residual radioactivity by using RESRAD code. When performing sensitivity analysis on probabilistic parameters, secondary evaluation is performed by assigning a single value for parameters classified as sensitive. However, several options may arise in the handling of nonsensitive parameters. Therefore, we compared the results of the first execution of RESRAD applying probabilistic parameters for each scenario with the results of the second execution applying a single value to sensitive parameters among the probabilistic parameters. In addition, we analyzed the effect of setting options for non-sensitive parameters. As a result, the effect on DCGL were different depending on the application scenario, the target radionuclides, and the input parameter selections. In terms of the overall evaluation period, the DCGL graph of the default option was generally shown as the most conservative except for some radionuclides. However, it will not necessarily be given priority in the aspect of the need to reflect site characteristics. The reason for selecting a probabilistic parameter is the availability of the parameter and the uncertainty of applying a single value. Therefore, as an alternative, it can be consistently applied to distribution as an option for non-sensitive parameters after sensitivity analysis.
Abstract
In the decommissioning of nuclear facilities, Derived Concentration Guideline Level (DCGL) derivation is necessary for the release of the facility after the site remediation, which also needs to be implemented in the stage of establishing a decommissioning planning. In order to derive DCGL, the dose assessment for the receptors can be conducted from residual radioactivity by using RESRAD code. When performing sensitivity analysis on probabilistic parameters, secondary evaluation is performed by assigning a single value for parameters classified as sensitive. However, several options may arise in the handling of nonsensitive parameters. Therefore, we compared the results of the first execution of RESRAD applying probabilistic parameters for each scenario with the results of the second execution applying a single value to sensitive parameters among the probabilistic parameters. In addition, we analyzed the effect of setting options for non-sensitive parameters. As a result, the effect on DCGL were different depending on the application scenario, the target radionuclides, and the input parameter selections. In terms of the overall evaluation period, the DCGL graph of the default option was generally shown as the most conservative except for some radionuclides. However, it will not necessarily be given priority in the aspect of the need to reflect site characteristics. The reason for selecting a probabilistic parameter is the availability of the parameter and the uncertainty of applying a single value. Therefore, as an alternative, it can be consistently applied to distribution as an option for non-sensitive parameters after sensitivity analysis.
참고문헌 (20)
- Criteria for Reuse of Site and Buildings after Completion of Decommissioning of Nuclear Facilities, "NSSC", Nuclear Safety and Security Commission, ~ (2021)
- Regulations on the Preparation of Decommissioning Plans for Nuclear Power Facilities, "NSSC", Nuclear Safety and Security Commission, ~ (2021)
- 변지향, "Derivation of preliminary derived concentration guideline levels for surface soil at Kori Unit 1 by RESRAD probabilistic analysis", Nuclear Engineering and Technology, 50(8), pp.1289~1297 (2018), 한국원자력학회
- Probabilistic Dose Analysis Using Parameter Distributions Developed for RESRAD and RESRAD-BUILD Codes, "NRC", U.S. Nuclear Regulatory Commission, ~, pp.NUREG (2000), CR-6676
- Rancho Seco License Termination Plan Chapter 6, Compliance with the Radiological Criteria for License Termination, "SMUD", Sacramento Municipal Utility District, ~ (2006)
- Development of Probabilistic RESRAD 6.0 and RESRAD-BUILD 3.0 Computer Codes, "NRC", U.S. Nuclear Regulatory Commission, ~, pp.NUREG (2000), CR-6697
- YAEC, "Yankee Nuclear Plant Station License Termination Plan, vol. 1" (2004), Yankee Atomic Electric Company
- CYAPC, "HADDAM NECK Plant License Termination Plan, vol. 4" (2006), Connecticut Yankee Atomic Power Company
- 서형우, "Calculation of Preliminary Site-Specific DCGLs for Nuclear Power Plant Decommissioning Using Hybrid Scenarios", Nuclear Engineering and Technology, 51(4), pp.1098~1108 (2019), 한국원자력학회[DOI]
- ZionSolutions, "Technical support document for potential radionuclides of concern during the decommissioning of the zion station, Rev 1", ~ (2012)
- Radionuclide Selection for DCGL Development, "PG&E", Pacific Gas and Electric Company, ~ (2012)
- Radionuclides for Consideration during Rancho Seco Site Characterization or Final Status Surveys, "SMUD", Sacramento Municipal Utility District, ~ (2005)
- 서형우, "Proposal for the list of potential radionuclides of interest during NPP site characterization or fi nal status surveys", Nuclear Engineering and Technology, 53(1), pp.234~243 (2021), 한국원자력학회[DOI]
- H. W. Seo, "Scenario options to calculation of derived concentration guideline levels for a multi-unit decommissioning site", Annals of Nuclear Energy, 133, pp.347~238 (2019)
- Development of Regulatory Requirements for Clearance of Radioactive Waste, "KINS", Korea Institute of Nuclear Safety, ~ (2002)
- Supplementation an V&V of Integrated Dose Assessment Code Package, "KINS", Korea Institute of Nuclear Safety, ~ (2014)
- Development of Technology in Radiation Safety Regulations, "KINS", Korea Institute of Nuclear Safety, ~ (2005)
- User's Manual for RESRAD Version 6, "ANL", Argonne National Laboratory, ~ (2001)
- Data Collection Handbook to Support Modeling Impacts of Radioactive Material in Soil and Building Structures, "ANL", Argonne National Laboratory, ~ (2015)
- Comparison of Dose Impacts from Alternative Exposure Scenario, "RSNGS", Rancho Seco Nuclear Generating Station, ~ (2005)