In 2017, a decision was made to permanently shut down Kori Unit 1, and preparations began to be made for its decontamination and decommissioning. The dismantling of the biological shields concrete, reactor vessel (RV), and reactor vessel internals (RVI) is crucial to the nuclear decommissioning process. These components were radiologically activated by the neutron activation reaction occurring in the reactor during its operational period. Because of the radioactivity of the RV and RVI of Kori Unit 1, remotely controlled systems were developed for cutting within the cavity to reduce radiation exposure. Specialized equipment was developed for underwater cutting operations. This paper focuses on modeling related to RVI operations using the MAVRIC code and the dose calculation for a diver entering the cavity. The upper and lower parts of the RVI are classified as low-level radioactive waste, while the sides that came into contact with the fuel are classified as intermediate-level radioactive waste. Therefore, the modeling presented in this paper only considers the RVI sides because the upper and lower parts have a minimal impact on the radiation exposure. These research findings are anticipated to contribute to enhancing the efficiency and safety of nuclear reactor decommissioning operations.

The decommissioning process of Kori Nuclear Power Plant No.1, which was permanently suspended in 2017, various studies and attention on the decommissioning of nuclear power plants and waste management are being focused. In particular, decommissioning of high-risk facilities should take into account both safety and economic aspects. Small defects in the decommissioning process may lead to major disasters, and the resulting economic losses will cause enormous damage at the national level. In order to prevent such damage, various decommissioning process simulations within a virtual environment should be performed, and process errors and results should be collected and analyzed through simulation to derive the optimal decommissioning scenario as possible. The platform introduced in this paper builds a virtual environment based on drawing and modeling data of Kori Nuclear Power Plant No.1 and automatically creates an optimized cutting path for dismantling the facility and internal structure, and simulates a cutting process similar to reality using Robot Arm. In addition, it is possible to derive and analyze a cutting process scenario by processing process results such as time required for work and cutting distance collected through simulation.

It is necessary to prepare for cutting and storing waste materials in the reactor vessel internals (RVI) for successful decommissioning of the nuclear power plant (NPP). Since RVI contain massive components and relatively highly activated, their decommissioning process should be conducted carefully in terms of radiological and industrial safety. To achieve efficient decommissioning waste management, this study presents radiation level of RVI and cutting optimization was performed for intermediate level waste. As a result of the radiation evaluation, a part of the core side and the upper part of RVI were evaluated as intermediate-level waste, and other components were evaluated as very low-level or lowlevel waste. For intermediate-level waste cutting, the minimum cutting method that can be put into a container was reviewed in consideration of the size, thickness, and cutting method of the interior product. The final segmentation parts are expected to be loaded into two storage containers.

After the permanent shutdown of K1 in 2017, decommissioning processes have attracted great attention. According to the current decommissioning roadmap, the dismantling of the activated components of K1 may start in 2026, following the removal of its spent fuel. Since the reactor vessel (RV) and reactor vessel internal (RVI) of K1 contain massive components and are relatively highly activated, their decommissioning process should be conducted carefully in terms of radiological and industrial safety. For achieving maximum efficiency of nuclear waste management processes for K1, we present activation analysis of the segmentation process and waste classification of the RV and RVI components of K1. For RVI, the active fuel regions and some parts of the upper and lower active regions are classified as intermediate-level waste (ILW), while other components are classified as low-level waste (LLW). Due to the RVI’s complex structure and high activation, we suggest various underwater segmentation techniques which are expected to reduce radiation exposure and generate approximately nine ILW and nineteen very low level waste (VLLW)/LLW packages. For RV, the active fuel region and other components are classified as LLW, VLLW, and clearance waste (CW). In this case, we suggest in-situ remote segmentation in air, which is expected to generate approximately forty-two VLLW/LLW packages.

원자력발전소 부품중 안전과 관련된 구조물은 지진하중하에서 그 건전성올 유지하도록 설계되어야 한다. 그중 원자로내부구조물부품은 l차 내진분류에 속하는 것으로써 지진하중하에서의 건전성이 발전소 안전과 경제적인 관점에서 매우 중요하다. 지금까지 이러한 원자로내부구조물의 모탤링에 대해서는 여러 사람들에 의해 연구되고 발표되었으나， 본 논문에서는 국내 발전소 중에서 Turn-key base로 건설되어 이미 가동 중에 있는 영광 1&2호기의 원자로내부구조물에 대한 안전정지지진하의 거동올 Global Beam Model 이라는 단순 화된 모델을 이용하여 분석하였다. 이 모델의 설정올 위해서 주요부품들을 double pendulum의 보요소로 표 현하였고， 이들 주요부품들의 특성해석을 범용유한요소해석코드인 ANSYS 에 의해 구하여 이를 상부 및 하 부에서 간격올 갖는 비선형스프링으로 모델링하였다. 또한 이 비선형스프링뿐아니라 원자로용기와 원자로내 부구조물부품들 사이의 유체동적현상을 묘사한 유체동력학적 coupling 에 의해 pendulum의 보요소를 서로 연결시켜 모델링을 하였다. 가진자료인 안전정지하중은 영광 1&2호기의 원자로용기 지지부에 가해지는 웅답 스펙트럼올 시간이력함수로 바꾸었으며， 이 모델과 가진 하중을 가지고 비선형해석 ∞de 인 KWUSTOSS 의 explicit Runge-Kutta-Gills algorithm을 이용하여 적분을 수행하므로써 안전정지지진하의 원자로 내부구조 물에 대한 거동을 구하여 이 구조물의 주요부품에 대한 내진검증 및 구조물 내부에 있는 핵연료집합체의 내진 해석올 위한 입력자료를 확보할 수 있었다. 그리고 본 연구에서 사용된 Global Beam Model 의 간편성 및 효 율성 과 explicit Runge-Kutta-Gills algorithm에 대 한 경 제 성을 확인할 수 있었다.

원자로내부 구조물은 유체속에 잠겨있기 때 문 에 동적해석시 이의 영향을 고려해야한다. 본 논문에서 는 지 진 및 배관파단에 대한 원자로내부구조물 의 동적해석을 위한 비선형해석 모 델 을 제시하였고 유체-구조불 상호 작용의 효과를 고려하는 방볍에 대하여 설 명하였다. 실제 해석을 통하여 유체一구조불 상호작용이 원자로내 부 구조 물 의 웅답에 미치는 영향을 조사한 결 과 지진해석시에 는 유체- 구조불 상호작용을 나타내 는 hydrodynamic coupling 항이 첨가됩으로 써 높은 응답이 나왔으나， 배관파단시에는 이와 반대의 결파가 나왔 다.