• 방사성폐기물학회지
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• 제17권1호
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• pp.15-28
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• 2019

고리 1호기는 원전해체 계획에 따라 영구정지 이후 가능한 한 빠른 시일 내에 원자로냉각재계통의 화학제염을 수행할 계획으로, 계통제염 기술 확보를 위해 한수원에서는 2014년부터 '원전 해체설계를 위한 냉각재계통 및 기기제염 상용기술개발' 연구과제를 통해 화학제염기술을 개발하고 있다. 본 연구를 위해 Lab. 규모 계통제염 공정장치를 제작하였으며, 계통제염 대상의 주요재료인 STS304, 316, 410, Alloy600, SA508을 사용하여 화학제염 공정실험을 수행하였다. 화학제염 공정실험의 목적은 산화-환원공정의 최적시간, 최적제염제 및 공정횟수를 도출하기 위함이다. 화학제염 공정실험은 과망간산-옥살산 기반의 단위공정 및 연속공정 실험, 과망간산+질산-옥살산 기반의 연속공정 실험으로 나누어 수행하였다. 그 결과 단위공정실험을 통해 최적공정 시간인 산화공정 5시간, 환원공정 4시간을 도출하였으며, 연속공정실험을 통해 최적제염제와 공정횟수를 도출하였다. 최적제염제는 산화제의 경우 $200mg{\cdot}L^{-1}$ 과망간산 + $200mg{\cdot}L^{-1}$ 질산이고, 환원제는 $2000mg{\cdot}L^{-1}$ 옥살산이며, 공정횟수는 STS304와 SA508의 경우 2 cycle, Alloy600의 경우 3 cycle 이상 수행하는 것이 적절할 것으로 평가되었다.

• 한국시뮬레이션학회:학술대회논문집
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• 한국시뮬레이션학회 2000년도 추계학술대회 논문집
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• pp.61-66
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• 2000

전력연구원에서 개량중인 한국원자력교육원 제 2호기 (KNPEC#2) 시뮬레이터의 검증을 위해 출력 연속변화 등 시나리오를 선정하여, 이에 대한 기준 데이터를 최적평가용 전산코드인 RETRAN과 MARS를 이용하여 생산하였다. 선정된 시나리오를 정확히 모사하기 위해 KNPEC#2 시뮬레이터의 대상호기인 영광 1,2호기 노심냉각계통 및 증기 계통을 상세 분할하였으며, 주요 기기 및 제어 계통을 모델링하였다. 모델링을 위해서 발전소 실제 운전자료를 활용하였으며, 필요시 설계자료와 유사호기인 고리 3,4호기 자료를 참고하였다. 끝으로 정상상태 및 비정상상태 운전조건과의 비교를 통해 모델링의 타당성을 확인한 후 각 시나리오에 따른 데이터를 생성하였다.

• 에너지공학
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• 제12권2호
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• pp.101-108
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• 2003

The purpose of this study is to develop an entrainment model of the Pressurized Water Reactor (PWR) U-tube Steam Generator (SG) for Main Steam Line Break (MSLB) analyses. Generally, the temperature of the inside containment vessel at MSLB is decreased by introducing the liquid entrainment effect. This effect makes a profit on the aspect of integrity evaluation for Equipment Environmental Qualification (EEQ) in the containment. However, the target plant, Kori unit 1 does not have the entrainment data. Therefore, this study has been performed. RETRAN-3D and LOFTRAN computer programs are used for the model development. There are several parameters that are used for the initial benchmark, such as Combustion Engineerings (CE) experimental data and the RETRAN-3D model which describes the test leg. A sensitivity study is then performed with this model in which the model parameters are varied until the calculated results provide reasonable agreement with the measured results for the entire test set. Finally, a multiplication factor has been obtained from the 95/95 values of the calculated (best-estimate) quality data relative to the measured quality data. With this new methodology, an additional temperature margin of about 40$^{\circ}C$ can be obtained. So, the new methodology is found to have an explicit advantage to EQ analyses.

• Nuclear Engineering and Technology
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• 제50권7호
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• pp.1088-1098
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• 2018

Kori unit #1, which is the first commercial nuclear power plant in Korea, was permanently shutdown in June 2017, and it is about to be decommissioned. Currently in Korea, researches on the decommissioning technology are actively conducted, but there are few researches on workers internal exposure to radioactive aerosol that is generated in the process of decommissioning nuclear power plants. As a result, the over-exposure of decommissioning workers is feared, and the optimal working time needs to be revised in consideration of radioactive aerosol. This study investigated the annual exposure limits of various countries, which can be used as an indicator in evaluating workers' internal exposure to radioactive aerosol during pipe cutting in the process of decommissioning nuclear power plants, and the growth and dynamics of aerosol. Also, to evaluate it, the authors compared/analyzed the cases of aerosol generated when activated pipes are cut in the process of nuclear power plants and the codes for evaluating internal exposure. The evaluation codes and analyzed data conform to ALARA, and they are believed to be used as an important indicator in deriving an optimal working time that does not excess the annual exposure limit.

• 방사성폐기물학회지
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• 제21권2호
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• pp.255-269
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• 2023

Compared to operational wastes, nuclear power plant (NPP) decommissioning wastes are generated in larger quantities within a short time and include diverse types with a wider range of radiation characteristics. Currently used 200 L drums and IP-2 type transport containers are inefficient and restrictive in packaging and transporting decommissioning wastes. Therefore, new packaging and transport containers with greater size, loading weight, and shielding performance have been developed. When transporting radioactive materials, radiological safety should be assessed by reflecting parameters such as the type and quantity of the package, transport route, and transport environment. Thus far, safety evaluations of radioactive waste transport have mainly targeted operational wastes, that have less radioactivity and a smaller amount per transport than decommissioning wastes. Therefore, in this study, the possible radiation effects during the transport from NPP to disposal facilities were evaluated to reflect the characteristics of the newly developed containers and decommissioning wastes. According to the evaluation results, the exposure dose to transport workers, handling workers, and the public was lower than the domestic regulatory limit. In addition, all exposure dose results were confirmed, through sensitivity analysis, to satisfy the evaluation criteria even under circumstances when radioactive materials were released 100% from the container.

• Nuclear Engineering and Technology
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• 제56권8호
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• pp.3359-3368
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• 2024

In the calculation of DCGLs using RESRAD code, the selection of input parameter values is paramount, which is basically possible when specific measures for selecting reuse scenarios and probabilistic evaluation methods are established. When referring to the impact of the age group considered in the environmental impact assessment among the existing operations of the plant, it may also need to be applied in the decommissioning project, and there will be considerations along with site reuse scenarios and probabilistic evaluations. Therefore, the main purpose of this study is to distinguish the types of exposure affected by residual radioactivity contamination during the process of deriving DCGL to be used in the final site release stage of NPPs and to evaluate them by reasonably assigning age group parameter values. In addition, the case of entering a single value for parameter values by age group and the case of entering probabilistic distributions were compared and analyzed.

• 방사성폐기물학회지
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• 제22권3호
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• pp.363-376
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• 2024

Kori Unit 1, the first commercial nuclear power plant (NPP) in Korea, was permanently shut down in 2017 and was scheduled for decommissioning. Various programs must be planned early in the decommissioning process to safely decommission NPPs. Radiological characterization is a key program in decommissioning and should be a high priority. Radiological characterization involves determining the decommissioning technology to be applied to a nuclear facility by identifying the radiation sources and radioactive contaminants present within the facility and assessing the extent and nature of the radioactive contaminants to be removed from the facility. This study introduces the regulatory requirements, procedures, and implementation methods for radiological characterization and proposes a methodology to link the results of radiological characterizations for each stage. To link radiological characteristics, this study proposes to conduct radiological characterization in the decommissioning phase to verify the results of radiological characterization in the transitional phase of decommissioning NPPs. This enables significantly reducing the scope and content of radiological characterization that must be performed in the decommissioning phase and maintaining the connection with the previous phase.

• 한국방사선학회논문지
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• 제12권3호
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• pp.297-304
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• 2018

미국의 원전해체 지침서인 MARSSIM과 MARLAP에서는 의사결정 전 부지조사를 계획하고, 계획한 조사를 시행하는데 Data Life Cycle의 사용을 권장하고 있다. 부지조사 계획단계에서 설정되는 데이터품질목표(DQO)는 부지조사 수행 및 설계의 모든 측면에서 얻을 수 있는 데이터를 최선으로 활용하는 방법을 제시하고, 부지조사 계획을 체계화하여 공식적으로 중요한 의사결정을 내리는데 필요한 정보를 얻을 수 있도록 한다. DQO의 일곱 과정 중 5~7단계에서는 앞선 단계에서 수집한 정보를 이용하여 합리적이고 신뢰성있는 의사결정을 내릴 수 있도록 부지조사를 설계하는 과정이다. 이 과정 중 설정되는 회색영역은 관심핵종에 대한 조사단위의 평균농도가 실제로 DCGL을 초과하지 않음에도 불구하고, 초과한다고 판단하여 제염활동과 같은 추가적인 활동을 하도록 결정내리는 Type II 의사결정 오류로 인한 결과가 미약할 것으로 생각되는 농도범위로 정의된다. 회색영역은 부지에서 수집한 Sample에 속한 특정 핵종의 평균농도와, 규제한도로서 설정될 수 있는 잔류방사능 유도농도(DCGL)를 이용하여 정할 수 있다. 회색영역을 설정함으로써 가장 자원효율적으로 부지조사계획을 설정할 수 있으며 의사결정 오류에 대한 영향을 최소화 할 수 있다. 선행연구로 도출된 고리 1호기의 DCGL을 이용하여 회색영역을 설정하고, 이를 이용해 올바른 의사결정을 내릴 수 있도록 하는 Sample의 농도평가 방법을 제시하였다.

• Journal of Radiation Protection and Research
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• 제41권3호
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• pp.196-205
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• 2016

Background: The emergency planning zone (EPZ) of the city of Busan is divided into the precautionary actions zone (PAZ) and the urgent protective action planning zone; which have a 5-km radius and a 20-km to 21-km radius from the nuclear power plant site, respectively. In this study, we assumed that a severe accident occurred at Shin-Kori nuclear unit 3 and evaluated the dispersion speed of radiological material at each distance at various wind speeds, and estimated the effective dose equivalent and the evacuation time of PAZ residents with the goal of supporting off-site emergency action planning for the nuclear site. Materials and Methods: The total effective dose equivalent, which shows the effect of released radioactive materials on the residents, was evaluated using the RASCAL 4.2 program. In addition, a survey of 1,036 residents was performed using a standardized questionnaire, and the resident evacuation time according to road and distance was analyzed using the VISSIM 6.0 program. Results and Discussion: According to the results obtained using the VISSIM and RASCAL programs, it would take approximately 80 to 252.2 minutes for permanent residents to move out of the PAZ boundary, 40 to 197.2 minutes for students, 60 to 232.2 minutes for the infirm, such as elderly people and those in a nursing home or hospital, and 30 to 182.2 minutes for those temporarily within the area. Consequently, in the event of any delay in the evacuation, it is estimated that the residents would be exposed to up to $10mSv{\cdot}h^{-1}$ of radiation at the Exclusion Area Boundaries (EAB) boundary and $4-6mSv{\cdot}h^{-1}$ at the PAZ boundary. Conclusion: It was shown that the evacuation time for the residents is adequate in light of the time lapse from the initial moment of a severe accident to the radiation release. However, in order to minimize the evacuation time, it is necessary to maintain a system of close collaboration to avoid traffic congestion and spontaneous evacuation attempts.

• Nuclear Engineering and Technology
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• 제19권1호
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• pp.34-41
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• 1987

본 논문은 부하추종운전노심의 1차원 해석방법과 3차원 해석방법을 비교하기 위한 것이다. 이 목적으로 본 논문에서는 유한차분법에 의거한 1차원 HLOFO 코드와 수정형 Borresen 소격모형에 의한 3차원 CMSNAC 코드를 개발했다. CMSNAC 코드는 100-50-100% 출력변화를 수반하는 12-3-6-3 부하추종운전에 대한 고리 1호기 노심의 3차원 출려분포와 반응도 변수를 계산하는데 이용했다. 3차원 계산결과는 중성자속.체적 가증법으로 구한 단면적 및 버클링 입력에 의거한 1차원적 HLOFO 계산결과와 비교되었으며, 이 비교로부터 1차원 HLOFO 계산이 정착도 면에서 다소 뒤떨어지지만 3차원 계산에 가까운 결과를 얻을 수 있다는 것을 보였다.