환경중 방사성 스트론튬 분석 방법 연구

이경진,황정래,정운관,Lee, Goung-Jin,Hwang, Jung-Lae,Chung, Woon-Kwan 대한방사선방어학회 1999 방사선방어학회지 Vol.24 No.3

환경 중에는 핵실험 및 원자력 발전소에서 방출되는 여러 가지 방사성 핵종들과 천연방사성 핵종들이 존재한다. 이 중에서 원자력발전소 운영과 관련하여, 환경 중의 인공방사성 핵종에 대한 관심이 높아지고 있다. 핵실험이나 원자력발전소와 관련된 인공방사선 핵종들은 주로 핵분열 생성물들로서, 그 수가 200여종에 이른다. 이 중에서도 $^{90}Sr$과 $^{137}Cs$은 선량특성상 특히 주목되어 왔다. 본 논문에서는 환경준위의 $^{90}Sr$ 정량 분석 방법에 대한 연구를 수행하였다. 환경 중의 $^{90}Sr$은 저준위이며, 특성 감마선과는 달리 연속 스팩트럼의 베타선원으로, $^{89}Sr$, $^{90}Y$ 및 다른 방사성 핵종들과 혼합되어 있기 때문에 정량적인 분석이 매우 어렵다. 저준위 방사성 스트론튬 분석을 위해서는 농축 과정 및 분석에 영향을 주는 타 방사성 핵종과의 화학적 분리과정이 필요하다. 그 동안 국내 여러 기관에서 공통적으로 스트론튬 회수율 산정을 위해 중량법을 사용하였고, 화학분리절차도 중량법을 사용하기에 적합하도록 개발하여 사용하였다. 최근 분석기기의 발달로 인해서, ppm 이나 ppb 단위의 안정원소 분석을 쉽게 할 수 있다는 점에 근거하여, 원자분광분석기기(ICP : Inductively Coupled atomic Plasma emission spectrophotometer)를 사용한 회수율 산정 및 그에 적합한 절차를 개발하였다. 개발된 절차는 기존의 중량법에 비해서 화학적 처리절차가 훨씬 간편하면서도 정확도가 높아서, 환경방사성 스트론튬의 정량분석에 적절히 사용될 수 있다. In the natural, there exist several kinds of radioactive isotopes. From atmospheric weapon tests and then some isotopes are naturally radioactivity above all things, nuclear power plant operation and man-made radioactive isotopes concern steadily growing in the environment. During the fission process of nuclear weapon tests and nuclear power plant operation, more than 200 radioactive isotopes are generated. Among them, $^{90}Sr$ and $^{137}Cs$ has been regarded as very important isotopes due to characteristics. In this paper, a quantitative analysis method of environment low level $^{90}Sr$ is studied. Radioactivity level of the environmental $^{90}Sr$ is very low, and it emits continuous beta spectrum, and $^{90}Sr$ exists together with $^{89}Sr$, $^{90}Y$ and other radioactive isotopes. It very difficult to make the quantitative analysis of $^{90}Sr$. For the analysis of low level radioactive strontium, enrich and chemical separation of strontium from the other radioactive isotopes are needed. For the estimation of strontium recovery ratio, so called SGAT(Strontium Gravimetric Analysis Technique) was generally used among the domestic research groups, and chemical procedures were developed appropriation for the SGAT, Recently, by using ICP(Inductively Coupled atomic Plasma emission spectrophotometer), amounts of stable atoms can be measured easily and accurately to the extend of ppm or ppb. In this paper, new chemical procedures are developed to exploits the ICP technique. New developed method has simpler chemical treatment procedures and then it gives more accurate results compared with the traditional SGAT.

영광원자력발전소 주변의 지형 및 지질에 따른 $^{137}Cs$ 분포 및 거동에 관한 연구

한상준,이경진,김희근,Han Sang-Jun,Lee Goung-Jin,Kim Hee-Geun 한국방사성폐기물학회 2004 방사성폐기물학회지 Vol.2 No.4

This paper shows our experiment is performed to understand the exposure tendency of $^{137}Cs$ according to the height of area and also, to supplement it by considering chemical characters of $^{137}Cs$ exposed to the soil. The samples we use for this experiment are from the general flat area of Yeonggwang county where it has NPPs, the high places of Keumjung & Bulgap mountains, and Naejan mountain where it is quite far from the NPPs. The data from this experiment show that the exposure of $^{137}Cs$ is not harmful since its range is around 252 Bq/kg-dry in most of sampled soils such as from the general flat area, the high place of Keumjung mountain where is 2 km away from the NPPs, the other high place of Bulgap mountain where is about 20 km away from the NPPs, and Naejan mountain where it is far from the NPPs. Not like the general flat area, however, the data show that the higher the area is the more $^{137}Cs$ is exposed. That is, at the top of mountains, the more $^{137}Cs$ is exposed compared to at the bottom area. It is almost $2{\~}6$ times more than the general flat area of Yeonggwang county where it has NPPs. The data also show that the spread of $^{137}Cs$ is deeply related to the geographical(the height of area, rainfall, etc..) factors and chemical factors of soils. As the geographical factors, there are far more chances to be exposed of $^{137}Cs$ at the high area of mountains through the air compared to at lower area and therefore, we can get more high-leveled readings of $^{137}Cs$ at the high area while it is low-leveled ones at the general flat area even if both of them have the same soil conditions. Regarding the chemical factors of soil, it is clarified that the CEC is the key factor. The CEC means the capability of sticking $^{137}Cs$ accumulated into the soil. Hence, the more CEC it has the more high-leveled readings of $^{137}Cs$ we get under the same geographical condition.

영광원전에서 가상 사고시 대기확산 평가

나만균,심영록,정철기,이경진,김승평,정성태,Na, Man-Gyun,Sim, Young-Rok,Jung, Chul-Kee,Lee, Goung-Jin,Kim, Soong-Pyung,Chung, Sung-Tai 대한방사선방어학회 2000 방사선방어학회지 Vol.25 No.2

현재 영광원전에서 정상운전중 기체 방사성물질의 대기확산 평가를 위해 XOQ_DW 코드가 이용되고 있다. 이 코드는 기본적으로 XOQDOQ 코드에 근거하여 개발되었으며, 정상운전 및 사고시 피폭평가를 수행하기 위하여, 사고시 대기확산을 평가하는 방법이 첨가되어야 한다. 사고시 대기확산을 평가하기 위해서 USNRC Reg. Guide 1.145에 기초하여 개발된 PAVAN 코드에 근거하여 가상 사고시 대기확산 코드인 XOQAR 코드가 개발되었다. 이 코드는 XOQ_DW 코드와의 인터페이스를 통하여 XOQ_DW 코드의 입력인 지형 모델 그리고 XOQ_DW 코드의 출력인 연평균 대기확산인자가 본 코드의 입력으로 이용되었다. 본 코드를 이용하여 제한구역경계와 저인구지대 경계에서 대기확산인자 값이 바다방향을 제외한 최대값은 각각 $1.33{\times}10^{-4}$와 $7.66{\times}10^{-6}$ sec/$m^3$이었다. 본 코드의 개발을 통하여 영광원전에서 정상운전 및 사고시 대기확산을 평가할 수 있는 코드 시스템을 갖추게 되었다. 또한 개발된 코드는 산악이 많은 우리나라 다른 발전소에 적용하기 위해 산악지형 입력변경을 통하여 적절히 사용될 수 있을 것이다. XOQ_DW code is currently used to assess the atmospheric dispersion fur the routine releases of radioactive gaseous effluents at Yonggwang nuclear power plants. This code was developed based on XOQDOQ code and an additional code is required to assess the atmospheric dispersion for potential accidental releases. In order to assess the atmospheric dispersion fer the accidental releases, XOQAR code has been developed by using PAVAN code that is based on Reg. Guide 1.145. The terrain data of XOQ_DW code inputs and the relative concentrations (X/Q) of XOQ_DW code outputs are used as the inputs of the XOQAR code through the interface with XOQ_DW code. By using this code, the maximum values of X/Q at exclusion area and low population zone boundaries except for sea areas were assessed as $1.33{\times}10^{-4}$ and $7.66{\times}10^{-6}$ sec/$m^3$, respectively. Through the development of this code, a rode system is prepared for assessing the atmospheric dispersion for the accidental releases as well as the routine releases. This developed code ran be used for other domestic nuclear power plants by modifying the terrain input data.

이차원의 대류-확산 현상 해석에서 업와인드 방식에 의한 수치적 확산을 줄이기 위한 방법 연구

이경진,김숭평 조선대학교 원자력연구소 1990 原子力硏究 Vol.4 No.-

In solving the convection-diffusion phenomena, it is common to use central difference scheme or upwind scheme. The central difference scheme has second order accuracy, while the upwind scheme is only first order accurte. However, since the variation rising in the convection-diffusion problem is exponential, central difference scheme ceased to be a good method for anything but extremely small values of Δx. At large values of Δx, which is all one can afford in most practical problems, it is the upwind scheme that gives more reasonable results than the central scheme. But in the conventional upwind scheme, since the accuracy is only first order, false diffusion is some what large, and when the real diffusion is smaller than the numerical diffusion, solutions may be very errorneous. So in this paper, a method to reduce the numerical diffusion of upwind schme is studied. Developed scheme uses same number of nodes as conventional upwind scheme, but it considers the direction of flow more sophistically. As a conclusion, the developed scheme shows very good results. It can reduce false diffusion greatly with the cost of small complexity. Also, algorithm of the developed scheme is presented at appendix.

국내 원자력 발전소의 위험도 평가를 위한 결말 분석 코드개발

이경진,김숭평 조선대학교 원자력연구소 1990 原子力硏究 Vol.4 No.-

In the events of hypothetical accidents in nuclear power plant, radioactive materials are released to the environments. The main purpose of this paper is to evaluate the health effects and property damage from the released radioisotopes. When the accidents are taken place, radioactive material behavior and characteristics are calculated in PRA level 2 study, and from it containment release groups of radioisotopes are characterized. The resulting release groups, frequencies, and release quantities are used as a input of ex-plant concequence analysis. In this paper, methodological study and several model survey for ex-plant consequence analysis are taken. The CRAC2 code is proved to be proper for explant consequence analysis. To apply the developed code for domestic nuclear power plants, several test runs are taken with domestic data. To verify the developed code package system, results are compared with those of Sandia National Laboratories. The results are well agree with the those of SNL. In conclusion, developed code package system can be applied to the domestic nuclear power plants in many fields. It is recommended from the experience of this study, to establish the domestic data base is essential for full scale ex-plant consequence analysis.

핵융합로 다이버터 냉각재 특성 연구

이경진 조선대학교 에너지.자원신기술연구소 1999 에너지·자원신기술연구소 논문지 Vol.21 No.1

The objects of the study are to develop conceptual design tool of fusion reactor divertor, and to develop assessment tool for ITER. In the beginning of 1988, conceptual design of ITER was started, and had finished in 1990. Through the study, several important issues were found. Some of them are related with divertor design. This research is dedicated to solve several problems related with divertor cooling system. FEM code to analyze thermal conduction and convection has been developed, and the thermal analysis method of divertor design has been syudied, and characteristics of coolant materials have been studied and analyzed, and feasibility studies of coolant options has been performed.

A Study on the Environmental Radioactive Strontium Analysis

Hwang,Jung-Lae,Lee,Goung-Jin,Chung,Woon-Kwan 대한방사선 방어학회 2000 방사선방어학회지 Vol.24 No.3

환경 중에는 핵실험 및 원자력 발전소에서 방출되는 여러가지 방사성 핵종들과 천연방사성 핵종들이 존재한다. 이 중에서 원자력발전소 운영과 관련하여, 환경 중에 인공방사성 핵종에 대한 관심이 높아지고 있다. 핵실험이나 원자력발전소와 관련된 인공방사선 핵종들은 주로 핵분열 생성물들로서, 그 수가 200여종에 이른다. 이중에서도 Sr 과 Cs은 선량특성상 특히 주목되어 왔다. 본 논문에서는 환경준위의 Sr 정량 분석방법에 대한 연구를 수행하였다. 환경 중에 ?Sr은 저준위이며, 특성 감마선과는 달리 연속 스팩트럼의 베타선원으로 Sr, Y 및 다른 방사성 핵종들과 혼합되어 있기 때문에 정량적인 분석이 매우 어렵다. 저준위 방사성 스트론튬 분석을 위해서는 농축 과정및 분석에 영향을 주는 타 방사성 핵종과의 화학적 분리과정이 필요하다. 그 동안 국내 여러기관에서 공통적으로 스트론튬 회수율 산정을 위해 중량법을 사용하였고, 화학분리절차도 중량법을 사용하기에 적합하도록 개발하여 사용하였다. 최근 분석기기의 발달로 인해서, ppm 이나 ppb 단위의 안정원소 분석을 쉽게 할 수 있다는 점에 근거하여, 원자분광분석기기(ICP: Inductively Coupled atomic Plasma emission spectrophotometer)를 사용한 회수율 산정 및 그에 적합한 절차를 개발하였다. 개발된 절차는 기존의 중량법에 비해서 화학적 처리절차가 훨씬 간편하면서도 정확도가 높아서, 환경방사성 스트론튬의 정량분석을 적절히 사용될 수 있다. In the natural there exist several kinds of radioactive isotopes. From atmospheric weapon tests and then some isotopes are naturally radioactivity above all things, nuclear power plant operation and man-made radioactive isotopes concern steadily growing in the environment. During the fission process of nuclear weapon tests and nuclear power plant operation, more than 200 radioactive isotopes are generated. Among them, Sr and Cs has been regarded as very important isotopes due to characteristics. In this paper, a quantitaive analysis method of environment low level Sr is studied. Radioactivity level of the environmental Sr is very low, and it emits continuous beta spectrum, and Sr exists together with Sr, Y and other radioactive isotopes. It very difficult to make the quantitative analysis of Sr. For the analysis of low level radioactive strontium, enrich and chemical separation of strontium from the other radioactive isotopes are needed. For the estimation of strontium recovery ratio, so called SGAT(Strontium Gravimetric Analysis Technique) was generally used among the domestic research groups, and chemical procedures were developed appropriation for the SGAT. Recently, by using ICP(Inductively Coupled atomic Plasma emission spectrophotometer), amounts of stable atoms can be measured easily and accurately to the extend of ppm or ppb. In this paper, new chemical procedures are developed to exploits the ICP technique. New developed method has simpler chemical treatment procedures and then it gives more accurate results compared with the traditional SGAT.

A Study on the Diffusion of Gaseous Radioactive Effluents Based on the Statistical Method

Na,Man-Gyun,Lee,Goung-Jin 대한방사선 방어학회 1998 방사선방어학회지 Vol.23 No.4

국내 원전에 적용하기 위한 기체 방사성 물질 확산 및 피폭 평가 코드를 개발하였다. 정상 운전에 의한 기체 방사성 물질 확산 및 피폭 평가에는 직선 궤도 가우시안 플륨 모델을 사용하는 XOQDOQ 코드가 사용되어 왔다. 본 연구에서는 이 코드의 발전소 주변 지역에서의 바람 방향의 영향, 산악 지형에 대한 모델, 습식 침적에 대한 개선이 이루어졌다. 현실적인 유효 고도 보정 및 산악 침투 모델을 통해서 산악 지형에 대한 고려를 하였고, 바람 발생 확률 빈도를 수정하여 직선궤도 모델을 보완하였다. 개발된 코드는 영광원전의 주민피폭선량평가를 위해 채택되었으며, 산악이 많은 우리 나라 다른 발전소에 적용하기 위해 산악지형 입력변경을 통하여 적절히 사용될 수 있을 것이다. A diffusion model of radioactive gaseous effluents is improved to apply for domestic nuclear power plants. Up to now, XOQDOQ computer code package developed by U. S NRC has been used for the assessment of radioactive plume dispersion by normal operation of domestic nuclear power plants. XOQDOQ adopts the straight-line Gaussian plume model which was basically derived for the plane terrain. However, since there are so many mountains in Korea, the several shortcomings of XOQDOQ are improved to consider the complex terrain effects. In this work, wind direction change is considered by modifying the wind rose frequency using meteorological data of the local weather stations. In addition, an effective height correction model, a plume reduction model due to plume penetration into mountain, and a wet deposition model are adopted for more realistic assessments, the proposed methodology is implemented in Yongkwang nuclear power plants, and can be used for other domestic nuclear power plants.

A Study on the Oceanic Diffusion of Liquid Radioactive Effluents based on the Statistical Method

Kim,Soong-Pyung,Lee,Goung-Jin 대한방사선 방어학회 1998 방사선방어학회지 Vol.23 No.1

영광 원전 지역에 적용될수 있는 액체 방사성 물질의 확산 모델을 개발하였다. 영광에서의 해양 확산조건은 매우 복잡하기 때문에 수치적 모델을 적용하는 것은 매우 어렵다. 따라서 비교적 단순하면서도 신뢰성 있는 미규제 지침 1.113에서 제시한 통계적 모델을 적용하였다. 이를 통해, 발전소 운전조건이나, 피폭경로에 따른 희석 인자를 계산할 수 있는 컴퓨터 코드를 개발하였다. 액체 방사성 물질의 확산에 대해서, 혼합 범위를 따라 근거리 혼합 모델과 원거리 혼합 모델로 구분하여 모델을 개발하였다. 근거리 혼합 현상은 부력과 초기 운동량 및 난류에 의해 결정된다. 원거리 혼합에서는 대기 중의 구름확산과 유사하게 가우시안푸륨 모델을 적용할 수 있다. 서로 다른 피폭 경로에 대해 물리적 타당한 적분을 수행함으로서, 경로에 따른 희석인자를 구할 수 있었다. 개발된 모델을 사용하여 계산한 결과에 의하면, 현생 영광 ODCM에 사용되는 희석인자는 상당히 과평가되어 있음을 알 수 있다. A diffusion model of radioactive liquid effluents is developed and applied for YGN NPP's site, based on the Gaussian plume type model. Due to the complexity of oceanic diffusion characteristics of YGN site, a simple and reliable statistical model based on Reg. Guide 1.113 is developed. Also, a computer code package to calculate dilution factors as a function of plant operation conditions and pathway of radioactive materials. A liquid effluents diffusion model is developed by dividing the diffusion range into two categories, i.e., a near field mixing region and a far field maxing region. In the near field, the initial mixing is affected by a buoyance force, a high initial turbulence and momentum which is characterized by a plant operation condition and environmental conditions. The far field mixing is similar to gaseous effluents diffusion. So, beyond the near field region, welknown Gaussian plume model was adopted. A different area averages of Gaussian plume equation was taken for each radioactive exposure pathway. As a result, we can get different dilution factors for different pathways. Results shows that present dilution factors used for YGN ODCM is too much overestimated compared with dilution factors calculated with the developed model.