본 논문에서는 몬스터에게 붙잡히지 않고 키를 찾아서 연구소를 탈출하는 공포 방탈출 게임을 제안한다. 제 안하는 게임을 진행한30명의 게임 플레이 로그 데이터 분석 결과와 설문조사 결과를 바탕으로, 제안하는 게 임의 특징을 분석한 결과는 다음과 같다. 첫째, 제안하는 게임은 다양한 아이템, 액션, 탈출 경로를 제공한다. 제안하는 게임이 숨을 곳도 많고 다양한 상호작용을 제공한다고 설문에서4점 이상 주었다. 또한, map의 footprint를 분석한 결과, 플레이어는 다양한 경로를 통해 키를 찾아서 탈출하였다. 둘째, 제안하는 게임은 외 관으로 기능을 추론할 수 있는 직관적인 오브젝트를 제공한다. 따라서, 플레이어는 시각적 공간 및 게임 아 이템 용도를 쉽게 파악하여 조작할 수 있다. 설문조사 결과에서, 플레이어는 조작감 관련 항목의 점수를4점 이상을 주었다. 셋째, 제안하는 게임에서 플레이어는 아이템이 충분할 때보다는 부족할 때 더 몰입을 잘 한 다. 게임 플레이 로그 데이터 분석 결과와 설문조사 결과에 따르면, 플레이어는 아이템이 부족할 때 더 크게 공포를 느끼고 상황에 몰입하여, 더 적극적으로 행동하게 되고 더 민감하게 반응한다.

The domestic Pressurized Heavy Water Reactor (PWHR) nuclear power plant, Wolsong Unit 1, was permanently shut down on December 24, 2019. However, research on decommissioning has mainly focused on Pressurized Water Reactors (PWRs), with a notable absence of both domestic and international experience in the decommissioning of PHWRs. If proper business management such as radiation safety and waste is not performed, it can lead to increased business risks and costs in decommissioning. Therefore, the assessment of waste volume and cost, which provide fundamental data for the nuclear decommissioning process, is a crucial technical requirement before initiating the actual decommissioning of Wolsong Unit 1. Decommissioning radiation-contaminated structures and facilities presents significant challenges due to high radiation levels, making it difficult for workers to access these areas. Therefore, technology development should precede decommissioning process assessments and safety evaluations, facilitating the derivation of optimal decommissioning procedures and ensuring worker safety while enhancing the efficiency of decommissioning operations. In this study, we have developed a program to estimate decommissioning waste amounts for PHWRs, building upon prior research on PWR decommissioning projects while accounting for the specific design characteristics of PHWRs. To evaluate the amount of radioactive waste generated during decommissioning, we considered the characteristics of radioactive waste, disposal methods, packaging container specifications, and the criteria for the transfer of radioactive waste to disposal operators. Based on the derived algorithm, we conducted a detailed design and implemented the program. The proposed program is based on 3D modeling of the decommissioning components and the calculation of the Work Difficulty Factor (WDF), which is used to determine the time weighting factors for each task. Program users can select the cutting and packaging conditions for decommissioning components, estimate waste amount based on the chosen decommissioning method, and calculate costs using time weighting factors. It can be applied not only to PHWRs, but also to PWRs and non-nuclear fields, providing a flexible tool for optimizing decommissioning process.

With the aging of nuclear power plants (NPPs) in 37 countries around the world, 207 out of 437 NPPs have been permanently shutdown as of August 2022 according to the IAEA. In Korea, the decommissioning of NPPs is emerging as a challenge due to the permanent shutdown of Kori Unit 1 and Wolsong Unit 1. However, there are no cases of decommissioning activities for Heavy Water Reactor (HWR) such as Wolsong Unit 1 although most of the decommissioning technologies for Light Water Reactor (LWR) such as Kori Unit 1 have been developed and there are cases of overseas decommissioning activities. This study shows the development of a decommissioning waste amount/cost/process linkage program for decommissioning Pressurized Heavy Water Reactor (PHWR), i.e. CANDU NPPs. The proposed program is an integrated management program that can derive optimal processes from an economic and safety perspective when decommissioning PHWR based on 3D modeling of the structures and digital mock-up system that links the characteristic data of PHWR, equipment and construction methods. This program can be used to simulate the nuclear decommissioning activities in a virtual space in three dimensions, and to evaluate the decommissioning operation characteristics, waste amount, cost, and exposure dose to worker. In order to verify the results, our methods for calculating optimal decommissioning quantity, which are closely related to radiological impact on workers and cost reduction during decommissioning, were compared with the methods of the foreign specialized institution (NAGRA). The optimal decommissioning quantity can be calculated by classifying the radioactivity level through MCNP modeling of waste, investigating domestic disposal containers, and selecting cutting sizes, so that costs can be reduced according to the final disposal waste reduction. As the target waste to be decommissioning for comparative study with NAGRA, the calandria in PHWR was modeled using MCNP. For packaging waste container, NAGRA selected three (P2A, P3, MOSAIK), and we selected two (P2A, P3) and compared them. It is intended to develop an integrated management program to derive the optimal process for decommissioning PHWR by linking the optimal decommissioning quantity calculation methodology with the detailed studies on exposure dose to worker, decommissioning order, difficulty of work, and cost evaluation. As a result, it is considered that it can be used not only for PHWR but also for other types of NPPs decommissioning in the future to derive optimal results such as worker safety and cost reduction.

Once a radioactive material is released from the nuclear power plant (NPP) by accident, it is necessary to understand the behavior of radioactive plume to protect residents adequately. For this, it is essential to measure the radiation dose rate around NPPs at important locations. Our previous study developed a movable radiation detector that can be installed quickly in an accident to measure gamma dose rate in areas where environmental radiation monitoring system is not installed. The data measured by the detector are transmitted to the server in real-time through LoRA wireless communications. There are two methods to use LoRA communications; one is self-network, and the other is the network provided by the mobile carrier. A signal receiver, called a gateway, should be equipped near the installation location of radiation detectors to use a self-network without using the mobile carrier’s system. In other words, the movable radiation detectors we made can function if there should be any gateway near them. The distance capable of communication between gateway and detector is about 8 km in an open area without significant obstacles. Korea has many significant obstacles, such as mountains around most NPPs. Thus, the gateways could be installed in the proper position before the accident to operate the movable radiation detectors without problems. If the gateway is located at a high position like a mountain top, it could cover a wide area. In this study, the elevation database in the area around the NPPs was collected and analyzed to determine where gateways should be installed. The analysis range is limited in the urgent protective action planning zone. The optimization was also performed to minimize the number of gateways.

뇌 3차원 T1 관상면 검사 시 ENCASE를 적용했을 때 CS 계수의 증가 시 영상획득 시간 변화와 영상의 질의 변화에 따른 유용성에 관하여 알아보고자 한다. 연구 대상은 본원을 내원한 30명의 환자를 대상으로 하였고, 1.5T MRI 장치로 진행하였으며, 24채널 두경부 코일을 사용하였다. 획득한 영상의 상대적신호강도비(rSI)와 상대적대조도비(rC)를 구하였으 며, MIPAV로 뇌실질과 뇌실의 체적을 측정하여 One-way Anova를 사용하여 정량적 분석을 하였고, p<0.05일 때 통계 적으로 유의한 것으로 해석하였다. 또한, 5점 리커트 척도를 이용하여 영상의 질에 대하여 정성적 분석을 하였고, 측정자 내 신뢰도를 확인하기 위해 ICC가 0.75 이상 나오면 측정자간 신뢰성이 높은 것으로 간주하였다. rSI와 rC 모두 p<0.05로 통계적으로 유의미한 차이를 보였고, 급내 상관계수가 0.75이상(p<0.05)으로 통계적으로 매우 높은 신뢰도를 나타냈다. MIPAV를 이용한 체적측정에서는 뇌실질과 뇌실의 체적의 차이는 p=1.000으로 통계학적으로 유의미한 차이는 없었고, 사후분석결과 또한 유의미한 차이를 보이지 않았으며. 급내 상관계수가 0.75이상(p<0.05)으로 통계적으로 매우 높은 신뢰도를 나타냈다. 또한, 정성적 평가에서는 CS 계수가 증가함에 따라 유의미한 차이가 있는 것으로 나타났다(p<0.001). 따라 서 ENCASE 기법을 이용한 3차원 T1 TFE 관상면 검사 시 CS 계수를 증가시킨다면 뇌의 체적 변화 없이 3차원 T1 시상면 영상보다 짧은 150초로 기존의 뇌 3차원 시상면 T1 기본 검사시간 260초 보다 짧은 영상획득 시간으로 진단적 가치가 높은 영상을 제공할 수 있을 것으로 사료된다.