• 한국대기환경학회지
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• 제31권6호
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• pp.573-584
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• 2015

In this study, the atmospheric dispersion of radioactive material ($^{137}Cs$) was simulated with regard to its impact within a 50-km radius from the Kori Nuclear Power Plant (NKPP) based on two different types of models (the non-steady-state puff model CALPUFF and the lagrangian model HYSPLIT) during the spring of 2012 (May 2012). The dispersion distribution of $^{137}Cs$ calculated in the CALPUFF model was similar to that of the HYSPLIT model, but the magnitudes of differences in its spatio-temporal concentrations between the two models were different. The $^{137}Cs$ concentrations simulated by the CALPUFF were significantly lower than those of the HYSPLIT due to a limitation of puff models (e.g. puff size growth over time). The CALPUFF had the advantage of determining the dispersion of radioactive materials and their impacts on the surrounding regions, compared with the HYSPLIT that had high concentrations of $^{137}Cs$ in only small local areas with the movement of air masses along the local winds.

• 한국지하수토양환경학회지:지하수토양환경
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• 제19권4호
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• pp.12-22
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• 2014

This study evaluated the pattern of groundwater fluctuation in cyrstalline rock using time series and factor analyses. From the results, groundwater level for the 18 wells was classified into 4 types reflecting the hydrogeological properties and rainfall event. Type 1 (DB1-5, DB1-6, DB2-2, KB-10, KB-13) was significantly influenced by groundwater flow through water-conducting features, whereas type 2 (DB1-3, DB1-7, KB-1~KB-3, KB-7, KB-11, KB-14, KB-15) was affected by minor fracture network as well as rainfall event. Type 3 (DB1-1, DB1-2) was mainly influenced by surface infiltration of rainfall event. Type 4 (DB1-8, KB-9) was reflected by the irregular variation of groundwater level caused by anisotropy and heterogeneity of crystalline rock.

• 한국지하수토양환경학회지:지하수토양환경
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• 제22권4호
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• pp.33-48
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• 2017

An optimum disposal plan of disused sealed radioactive sources (DSRSs) should be established to ensure long-term disposal safety at the low- and intermediate-level radioactive waste (LILW) disposal facility in Gyeongju. In this study, an optimum disposal system was suggested and preliminary post-closure safety assessment was performed. The DSRSs disposal system was composed of a rock cavern and near surface disposal facilities at the Gyeongju LILW disposal facility. The assessment was conducted using GoldSim program, and probabilistic assessment and sensitivity analysis were implemented to evaluate the uncertainties in the input parameters of natural barriers. Deterministic and probabilistic calculations indicated that the maximum dose was below the regulatory limits ($0.1mSvyr^{-1}$ for the normal scenario, $1mSvyr^{-1}$ for the well scenario). It was concluded that the DSRSs disposal system would maintain environmental safety over a long-time. Moreover, the partition coefficient of Np in host rock, Darcy velocity in host rock, and density of the host rock were the most sensitive parameters in predicting exposure dose in the safety assessment.

• Journal of Radiation Protection and Research
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• 제41권1호
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• pp.7-14
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• 2016

연구배경: 본 연구는 일본 후쿠시마 원전사고 이후 원전사고 및 방사능 오염에 대한 우리 국민들의 인식도를 확인하기 위한 목적으로 진행되었다. 재료 및 방법: 설문조사는 수도권에 거주하는 성인 600명을 대상으로 하였다. 결과 및 논의: 연구 결과, 대다수 국민들은 일본 원전사고로 인한 방사능 누출이 우리나라에 영향을 미치고 있다고 우려하였다. 식품, 특히 수산물의 방사능 오염에 대한 우려가 높았고, 선호하는 정보 취득원은 TV(49.8%)와 인터넷 매체(31.3%)였다. 한편 다수의 국민들은 일본 원전사고 및 방사능 오염 정보가 충분히 제공되지 않았고, 원전사고 이후 우리 정부의 대응조치를 잘 모르고 있는 것으로 나타났다. 또한 국민 대다수가 식품 환경 등의 방사능 오염 정도와 안전성에 대한 정보제공 강화가 가장 중요한 것으로 인식하고 있었다. 결론: 본 연구 결과는 향후 방사능에 대한 올바른 인식 확립과 방사능 안전사고 리스크커뮤니케이션을 위한 유용한 자료로 활용될 수 있을 것으로 기대된다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2004년도 추계학술발표회 발표논문집
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• pp.793-794
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• 2004

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1999년도 추계학술발표회요약집
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• pp.277-277
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• 1999

• Journal of Radiation Protection and Research
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• 제29권1호
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• pp.41-48
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• 2004

A safety assessment code, called SAGE (Safety Assessment Groundwater Evaluation), has been developed to describe post-closure radionuclide releases and potential radiological doses for low- and intermediate-level radioactive waste (LILW) disposal in an engineered vault facility in Korea. The conceptual model implemented in the code is focused on the release of radionuclide from a gradually degrading engineered barrier system to an underlying unsaturated zone, thence to a saturated groundwater zone. The radionuclide transport equations are solved by spatially discretizing the disposal system into a series of compartments. Mass transfer between compartments is by diffusion/dispersion and advection. In all compartments, radionuclides ate decayed either as a single-member chain or as multi-member chains. The biosphere is represented as a set of steady-state, radionuclide-specific pathway dose conversion factors that are multiplied by the appropriate release rate from the far field for each pathway. The code has the capability to treat input parameters either deterministically or probabilistically. Parameter input is achieved through a user-friendly Graphical User Interface. An application is presented, which is compared against safety assessment results from the other computer codes, to benchmark the reliability of system-level conceptual modeling of the code.

• 한국세라믹학회지
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• 제43권3호
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• pp.148-151
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• 2006

In order to examine the process parameters for the vitrification of Low and Intermediate Level radioactive Waste (LILW) generated from nuclear power plants, measurements of several melt properties was performed for four selected glasses containing simulated waste. Electrical conductivity and viscosity were determined at temperatures ranging from 1123 to $1673^{\circ}C$. The temperature dependences of both properties in the molten state showed a similar behavior in which their values decrease as the temperature increases. The values of the electrical conductivity and viscosity at a temperature of 1423K adopted in an induction cold crucible melter process were $0.27{\sim}0.42$ S/cm and $9.8{\sim}42$ dPas, respectively.

• Nuclear Engineering and Technology
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• 제36권3호
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• pp.263-275
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• 2004

For the safe management of nuclear facilities, including a radioactive waste repository, data about the facility site and the surrounding environment must be collected and managed systematically. This is particularly true for a radwaste repository, which has to be institutionally controlled for a long period after closure. The objectives of this study are (1) to establish a systematical management plan for information about a radwaste repository site and its environment, and (2) to design a database management program for this information, based on the Relative Database Management System (RDBMS). The spatial data are designed by the geodatabase, which is a new object, based on the RDBMS, to manage spatial information related to the database. To meet this requirement, a new program called 'Site Information and Total Environmental data management System (SITES)' is being developed. The scope that produced from the first step of the present study for development of the SITES is introduced. The database is designed to combine spatial and attribute data, and is designed for the establishment of the Geographic Information System (GIS). The hardware and software systems are designed with consideration given to the total data management of the items within the radioactive environment.

• Journal of Radiation Protection and Research
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• 제22권4호
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• pp.309-317
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• 1997

비파괴적인 방법으로 방사성폐기물드럼에 대한 핵종분석을 수행할 때 드럼내 매질에 의한 방사선의 감쇠에 의해 핵종분석장치로 측정한 계수값은 실제 드럼내 방사능에 의한 계수값보다 작게 나타나 결과적으로 방사능의 측정결과가 과소평가된다. 그러므로 드럼내 매질에 의한 감쇠를 보정해 주어야 하는데 감쇠 보정방법은 드럼내 매질의 분포나 매질의 밀도에 따라 달리 적용해야 한다. 본 연구에서는 원자력발전소에서 발생하는 드럼 종류별로 모델드럼을 제작한 후 모델드럼에 표준감마선원을 넣고 핵종분석장치를 이용해 측정을 하여 드럼내 매질의 밀도를 구하였고, 이 값을 실제 매질의 밀도와 비교해 드럼종류에 따라 매질에 의한 최적의 감쇠 보정방법을 결정하였다. 그 결과 잡고체드럼의 경우에는 전송선원 보정방법과 평균밀도 보정방법, 차폐잡고체드럼의 경우 전송선원 보정방법과 두 감마선피크비교 보정방법이 최적의 감쇠 보정방법임을 알 수 있었고, 고밀도드럼인 폐수지, 농축폐액 및 폐필터드럼의 경우에는 평균밀도 보정방법과 두 감마선피크비교 보정방법을 사용해 드럼내 매질의 감쇠를 보정할 수 있다.