The transportation of spent nuclear fuel between management stages is expected, and the transportation workers may be exposed to radiation. When transporting spent nuclear fuel, the ALARA principle must be observed for the workers. The objective of this study is to assess a radiation dose for workers transporting spent nuclear fuel using metal overpacks. For this objective, the cask to be handled was selected and the radiation source term was set. Then, the radiation exposure scenario for the transportation workers was defined. Finally, the dose rates for each location of operation were assessed using Monte Carlo simulations, and collective doses were derived for each operation considering the radiation exposure scenario. Each worker performed 11 operations to transport spent nuclear fuel to other facilities and was exposed to a total of 1.138 man-mSv. The operation of removing the bottom shield ring resulted in the highest radiation exposure at 0.503 man-mSv. In contrast, the operation of installing the impact limiter resulted in the lowest radiation exposure at 0.0009 man-mSv. The results of this study can be used to strengthen radiation protection measures for workers transporting spent nuclear fuel in dry storage facilities using metal overpacks.

In this study, the time to endure after conducting a test pressure test was analyzed according to the hose development length of the household hose reel indoor fire hydrant according to the apartment area. First, when the household area is 50㎡, a household hose reel indoor fire hydrant is installed inside the bathroom, and the hose is bent in a circular shape to the farthest fire point, and the test pressure is found to be inadequate only when the hose development length is 5m. When the household area of an apartment is 84㎡. It was found that the test pressure was inappropriate only when the hose deployment length was 5m with the hose bent in a circular shape to the farthest point by installing a household hose reel indoor fire hydrant inside the bathroom. When the hose deployment length was 15m, the average experimental value was 3.9 Mpa and the water pressure resistance time was 8 min. It was found that the test pressure and holding time were suitable for all of the working pressure of 0.7 Mpa, the inner diameter of the hose 25mm and 32mm, and the hose deployment length. When the installation of the hose reel indoor fire hydrant hose was 3 Mpa, the internal diameter of the hose was 25mm, 32mm, and the length of the hose deployment were all suitable.

This project aimed to understand the near-infrared (NIR), intensity, and reflectivity characteristics of LiDAR for measuring retroreflectivity and to understand the correlation between the characteristics of LiDAR and retroreflectivity. A 600 m-testbed was investigated using a survey vehicle equipped with LiDAR, and the testbed retroreflectivity and LiDAR data measurement values were compared. The reflectivity and intensity at night were not affected by sunlight compared with daytime, enabling stable data collection. However, NIR reacted very sensitively to sunlight, and the difference between daytime and nighttime NIR values was very large. In addition, by comparing the absolute error between the retroreflectivity and LiDAR data, we observed that the reflectivity was consistent with the data difference between day and night, and it was not significantly affected by sunlight. However, the intensity showed that the daytime measurement data were more scattered than the nighttime measurement data, resulting in low-precision collection stability caused by sunlight. An analysis of the correlation between retroreflectivity and LiDAR data using 40 data points revealed that the reflectivity and intensity data at night were highly correlated with retroreflectivity, with a P-value of less than 0.05. Reflectivity and intensity values at night correlate with retroreflectivity. The NIR light is sensitive to sunlight. Thus, it can be used as a solar correction index for future retroreflectivity analyses using intensity.

PURPOSES : Recently, interest in radioactive accidents has increased due to domestic and international nuclear power plant accidents. In particular, local residents' concerns are increasing due to safety issues such as radioactive leaks at the Hanbit Nuclear Power Plant in South Korea. As Gwangju Metropolitan City is not included in the emergency planning area set by the Nuclear Safety and Security Commission, there are significant limitations to establishing disaster prevention measures for nuclear power plant accidents. Considering the Fukushima and Hanbit nuclear power plant accidents, the improvement of Gwangju Metropolitan City's radioactive leak accident response manual is urgently required. This study aimed to establish disaster prevention measures to respond to nuclear power plant accidents in Gwangju Metropolitan City in the event of a Hanbit Nuclear Power Plant accident and to improve resident protection measures by estimating the arrival time of radioactive materials and radiation dosage through a nuclear power plant accident simulation. Additionally, we aimed to supplement the on-site action manual for radioactive leaks at the Hanbit Nuclear Power Plant. METHODS : This study focused on establishing disaster prevention measures centered on Gwangju Metropolitan City in the event of a major accident such as a radioactive leak at the Hanbit Nuclear Power Plant. Simulations were conducted assuming a major accident such as a radioactive leak, measures to improve resident protection were established by calculating the arrival time of radioactive materials and radiation dosage in the Gwangju area in the event of a nuclear power plant accident, and on-site response action manuals were supplemented in response to a radioactive leak. RESULTS : This study considered the concerns of local residents due to the Fukushima nuclear power plant accident and the Hanbit nuclear power plant failure, conducted a simulation to derive the impact on Gwangju Metropolitan City, and examined the effectiveness of an on-site response manual for radioactive leaks to derive improvement measures. CONCLUSIONS : In the event of an accident at the Hanbit Nuclear Power Plant in Gwangju Metropolitan City, insufficient portions of the on-site response action manual should be supplemented, and close cooperation with local governments within the emergency planning area should be ensured to respond to radioactive disasters. Therefore, based on the revised on-site response action manual for radioactive leaks, close cooperation and a clear division of roles among local governments will enable effective resident protection measures to be implemented in the event of a radioactive disaster.

2011년 발생한 동일본대지진의 영향으로 후쿠시마 원자력발전소 폭파사고 이후 국제원자력기구(IAEA)의 방사선비상계획구역(EPZ) 확 대를 권고하였으며, 이에 따라 우리나라에서도 방사선비상계획구역(EPZ, Emergency Planning Zone)를 기존 반경 8~10km에서 20~30km 로 확대를 하였다. 이에 따라 방사선 비상시 대규모 대피에 관한 관심이 높아지며 원활한 대피를 위한 교통운영관리전략 수립이 필요 한 실정이다. 방사선 비상과 같은 대규모 재난이 발생하면 동시다발적인 대피수요가 발생하고 한정된 도로교통망에 차량이 집중되어 극심한 혼잡이 발생할 것으로 예상된다. 따라서, 본 연구에서는 교통분야에서 활용되는 도로운영관리전략 중 방사선비상시 적용 가능 한 전략 및 적용기준을 수립한다. 또한, 선정된 도로운영관리전략의 효과분석을 위하여 TOVA를 활용하였으며, Sub Network 기능으로 대상지역의 네트워크를 추출 후 분석을 시행하였다. 방사선비상시 도로운영관리전략은 도로용량 증대, 통행속도 향상, 교통수요 관리 및 기타 등 네 가지로 구분하여 분류하였다. 이 중 우리나라에 도입되지 않은 역류차로제 전략 도입 효과분석을 수행하였다. 시뮬레이 션 대상지는 고리원자력 발전소의 사고가 발생한 것으로 가정하며, 대피인원은 원자력발전소에서 부산광역시로 이동하는 것으로 설정 하였다. 효과분석 결과, 시행시 120.6%의 교통량(시간당 7,600대)과 117% 속도(30.21km/h → 65.55km/h)가 증가되는 것으로 분석되었다

The concrete silo dry storage system, which has been in operation at the Wolsong NPP site since 1992, consists of a concrete structure, a steel liner plate in the inner space, and a fuel basket. The silo system’s concrete structure must maintain structural integrity as well as adequate radiation shielding performance against the high radioactivity of spent nuclear fuel stored inside the storage system. The concrete structure is directly exposed to the external climatic environment in the storage facility and can be expected to deteriorate over time owing to the heat of spent nuclear fuel, as well as particularly cracks in the concrete structure. These cracks may reduce the radiation shielding performance of the concrete structure, potentially exceeding the silo system’s allowable radiation dose rate limits. For specimens with the same composition and physical properties as silo’s concrete structures, cracks were forcibly generated and then irradiated to measure the change in radiation dose rate to examine the effect of cracks in concrete structures on radiation shielding performance, and in the current state, the silo system maintains radiation shielding performance.

A procedure for minimizing the environmental burden and maximizing the efficiency of storage sites used for the final disposal of spent fuel has been proposed. In this procedure, fission products (highly mobile and producing heat) are collected, and uranium and TRU-RE (transuranium-rare earth) oxide are independently stored. The possibility and applicability of radiation measurement for monitoring the nuclear materials effectively throughout the process has been simulated and evaluated. For the simulation, the properties of the chemical processes were analyzed, the major radiation emitters were determined, and the production of nuclear materials by chemical reactions were evaluated. In each process, the content of nuclear material was changed by up to 20% to represent abnormal conditions. The results showed that the plutonium peak was matched with the change in the TRU content and the measured signal was changed linearly with respect to the content change of the plutonium. From the neutron measurement, a linear response of the TRU content variation was obtained. In addition, a logic diagram was developed for the nuclear monitoring. The integration of radiation detections is recommended for monitoring the process effectively and efficiently.

As the number of households with pets has increased worldwide, there is a growing trend of accepting pets as family members. Consequently, the pet food market has seen the emergence of concepts such as “human-grade,” “raw (PMR and BARF),” and “no synthetic additives” pet food. These concepts not only fulfill essential nutrients but also consider the health and habits of pets, a crucial aspect that should be at the forefront of our work. However, these types of pet food are prone to microbial contamination and component alterations caused by heat. Current studies and products have recently been developed overseas to apply non-thermal sterilization technologies to pet food commonly used in the food industry. In contrast, the domestic standards for non-thermal sterilization in pet food are insufficient. Therefore, a comprehensive review of non-thermal sterilization technologies, such as high-pressure processing (HPP), radiation, and plasma predominantly applied in the international pet food market, is deemed necessary. This review is expected to provide guidelines for non-thermal sterilization standards in domestic pet food, thereby laying the foundation for the safe production of raw pet food.

중재 시술의 발전으로, 노출된 방사선으로 인한 의료 방사선 중재 시술자에 미치는 건강 위협이 증대됨에 따라 시술 중 방사선 노출을 최소화하기 위한 관심과 노력이 요구되고 있다. 이에 대한췌장담도학회에서는 투시 장비를 이용한 중재 시술 중 의료 방사선 중재 시술자에게 미치는 방사선 노출을 최소화하기 위한 권고안을 개발하였다. 본 권고안은 방사선 차폐, 방사선 투시기와 방사선량의 관리, 방사선 노출 선량 한도 및 감시, 임신과 출산 총 4가지 분야로 나누어 중재 시술자에게 방사선 노출의 위험을 이해하기 위한 지식을 전달하고 실질적으로 수행해야 하는 권고사항을 명확히 제시하여 불필요한 방사선 노출을 피하기 위한 실용적인 접근이 가능하도록 구성되었다. 본 권고안을 통해 의료 방사선 중재시술자의 방사선 노출을 최소화하여 안전하고 효과적인 중재 시술이 이루어질 수 있기를 기대한다.

The Earth’s radiation belts, which extend from near the Earth to approximately geosynchronous orbit, contain highly energetic particles that actively interact with various plasma waves. This study reviews two numerical approaches to studying waveparticle interactions in the Earth’s radiation belts and discusses their respective advantages and limitations. The first approach involves diffusion simulations based on quasi-linear theory, which is well-suited for describing the collective dynamics of many particles from a statistical perspective. The second approach, test particle simulation, focuses on the detailed motion of individual particles, revealing nonlinear phenomena such as phase trapping and bunching. Both methods allow for the derivation of diffusion coefficients, which quantify the timescale of wave-particle interactions and help explain how particles either precipitate into the atmosphere or accelerate to higher energies in the Earth’s radiation belts. Additionally, these methodologies can be adapted to study the dynamics of planetary radiation belts, such as those around Jupiter and Saturn, by adjusting for the specific environmental parameters of each planet.