A safety assessment was performed on Kori Unit 1, which is planned to be decommissioned, and on the second-phase disposal facility of the Gyeongju low- and intermediate-level radioactive waste (LILW) repository using the RESRAD-OFFSITE code. Safety assessment for nuclear power plant decommissioning ...
A safety assessment was performed on Kori Unit 1, which is planned to be decommissioned, and on the second-phase disposal facility of the Gyeongju low- and intermediate-level radioactive waste (LILW) repository using the RESRAD-OFFSITE code. Safety assessment for nuclear power plant decommissioning and a radioactive waste repository have the common point that human exposure could occur due to radioactivity. However, there are distinct differences in regard to the assessment period, outcomes of interest, exposure situations. Therefore, safety assessment from a differentiated perspective is essential. From the perspective of nuclear power plant decommissioning, derivation of the derived concentration guideline level (DCGL) that satisfies the national site release criteria is essential for successful decommissioning. The Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM), a universally used decommissioning guideline, recommends performing a probabilistic analysis to confirm whether the site release criteria are satisfied, and this can be successfully accomplished using the RESRAD code. The resident farmer scenario and industrial worker scenario were employed, the radionuclides of concern and site-specific parameters were applied to the RESRAD-OFFSITE code to derive the preliminary exposure dose and DCGL for Kori Unit 1. The obtained results were compared with the results derived using the RESRAD-ONSITE code. The analysis results show that most of the radionuclides represent similar doses and DCGL values, but there are a few differences. Therefore, an analysis of the differences was performed by pathway analysis. The applicability of the RESRAD-OFFSITE code to the decommissioning of a nuclear power plant was studied.
From the perspective of radioactive waste disposal, a safety assessment was performed by applying the site-specific parameters of the Gyeongju LILW repository to the RESRAD-OFFSITE code. On the basis of the acceptance criteria of the repository, 13 radionuclides and gross alpha were selected as the radionuclides to be evaluated. In addition, the thermodynamic database (TDB) of Japan Atomic Energy Agency (JAEA), specific ion interaction theory (SIT), and groundwater data that reflect the impact of the operation of the disposal facility were applied to derive the solubility using the PHREEQC computational code. The distribution coefficient was derived for each disposal facility composition based on the sorption database (SDB) of JAEA. In addition to the solubility and distribution coefficient, the data of the disposal facility and repository site were analyzed and applied to the RESRAD-OFFSITE code. Results of safety assessment confirmed that sufficient safety was secured, as an exposure dose corresponding to 3.8% of the dose limit of 0.1 mSv/yr was generated. To obtain more reliable safety assessment results, a sensitivity analysis of the dose was conducted by varying the geochemical parameters. Although the dose changed as the geochemical parameters were varied, it was confirmed that the dose limit was satisfied. A comprehensive and differentiated safety assessment methodology was established in terms of nuclear power plant decommissioning and radioactive waste disposal using the RESRAD-OFFSITE code. Therefore, the possibility of applying the RESRAD-OFFSITE code to various situations, such as the short and long term and the location of the receptor (inside or outside the site) was confirmed. The established methodology makes it easy to obtain and apply research results. In addition, if additional site-specific data are applied, more reliable safety assessment results can be quickly derived.
A safety assessment was performed on Kori Unit 1, which is planned to be decommissioned, and on the second-phase disposal facility of the Gyeongju low- and intermediate-level radioactive waste (LILW) repository using the RESRAD-OFFSITE code. Safety assessment for nuclear power plant decommissioning and a radioactive waste repository have the common point that human exposure could occur due to radioactivity. However, there are distinct differences in regard to the assessment period, outcomes of interest, exposure situations. Therefore, safety assessment from a differentiated perspective is essential. From the perspective of nuclear power plant decommissioning, derivation of the derived concentration guideline level (DCGL) that satisfies the national site release criteria is essential for successful decommissioning. The Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM), a universally used decommissioning guideline, recommends performing a probabilistic analysis to confirm whether the site release criteria are satisfied, and this can be successfully accomplished using the RESRAD code. The resident farmer scenario and industrial worker scenario were employed, the radionuclides of concern and site-specific parameters were applied to the RESRAD-OFFSITE code to derive the preliminary exposure dose and DCGL for Kori Unit 1. The obtained results were compared with the results derived using the RESRAD-ONSITE code. The analysis results show that most of the radionuclides represent similar doses and DCGL values, but there are a few differences. Therefore, an analysis of the differences was performed by pathway analysis. The applicability of the RESRAD-OFFSITE code to the decommissioning of a nuclear power plant was studied.
From the perspective of radioactive waste disposal, a safety assessment was performed by applying the site-specific parameters of the Gyeongju LILW repository to the RESRAD-OFFSITE code. On the basis of the acceptance criteria of the repository, 13 radionuclides and gross alpha were selected as the radionuclides to be evaluated. In addition, the thermodynamic database (TDB) of Japan Atomic Energy Agency (JAEA), specific ion interaction theory (SIT), and groundwater data that reflect the impact of the operation of the disposal facility were applied to derive the solubility using the PHREEQC computational code. The distribution coefficient was derived for each disposal facility composition based on the sorption database (SDB) of JAEA. In addition to the solubility and distribution coefficient, the data of the disposal facility and repository site were analyzed and applied to the RESRAD-OFFSITE code. Results of safety assessment confirmed that sufficient safety was secured, as an exposure dose corresponding to 3.8% of the dose limit of 0.1 mSv/yr was generated. To obtain more reliable safety assessment results, a sensitivity analysis of the dose was conducted by varying the geochemical parameters. Although the dose changed as the geochemical parameters were varied, it was confirmed that the dose limit was satisfied. A comprehensive and differentiated safety assessment methodology was established in terms of nuclear power plant decommissioning and radioactive waste disposal using the RESRAD-OFFSITE code. Therefore, the possibility of applying the RESRAD-OFFSITE code to various situations, such as the short and long term and the location of the receptor (inside or outside the site) was confirmed. The established methodology makes it easy to obtain and apply research results. In addition, if additional site-specific data are applied, more reliable safety assessment results can be quickly derived.
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#방사성폐기물 RESRAD 코드
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