Pressurized Heavy Water Reactors (PHWR) have stored ion exchange resins, which are used in deuteration, dehydrogenation systems, liquid waste treatment systems, and heavy water cleaning systems, in spent resin storage tanks. The C-14 radioactivity concentration of PHWR spent resin currently stored at the Wolseong Nuclear Power Plant is 4.6×10E+6 Bq/g, which exceeds the limited concentration of low-level radioactive waste. In addition, when all is disposed of, the total radioactivity of C-14, 1.48×10E+15 Bq, exceeds the disposal limit of the first-stage disposal facility, 3.04×10E+14. Therefore, it is currently impossible to dispose of them in Gyeongju intermediate- and low-level disposal facilities. As to dispose of spent resins produced in PHWR, C-14 must be removed from spent resins. This C- 14 removal technology from the spent resin can increase the utilization of Gyeongju intermediate- and low-level disposal facilities, and since C-14 separated from the spent resin can be used as an expensive resource, it is necessary to maximize its economic value by recycling it. The development of C-14 removal technology from the spent resin was carried out under the supervision of Korea Hydro & Nuclear Power in 2003, but there was a limit to the C-14 removal and adsorption technology and process. After that, Sunkwang T&S, Korea Atomic Energy Research Institute, and Ulsan Institute of Science and Technology developed spent resin treatment technology with C-14-containing heavy water for the first and second phases from 2015 to 2019 and from 2019 to the present, respectively. The first study had a limitation of a pilot device with a treatment capacity of 10L per day, and the second study was insufficient in implementing the technology to separate spent resin from the mixture, and it was difficult to install on-site due to the enlarged equipment scale. The technology to be proposed in this paper overcomes the limitations of spent resin mixture separation and equipment size, which are the disadvantages of the existing technology. In addition, since 14CO2 with high concentration is stored in liquid form in the storage tank, only the necessary amount of C-14 radioactive isotope can be extracted from the storage tank and be used in necessary industrial fields such as labeling compound production. Therefore, when the facility proposed in this paper is applied for treating mixtures in spent resin tanks of PHWR, it is expected to secure field applicability and safety, and to reflect the various needs of consumers of labeled compound operators utilizing C-14.

After melting glass at a high temperature of about 1,100 degrees in the Cold Crucible Induction Melter (CCIM) of the vitrification facility, radioactive waste is fed into the CCIM to vitrify radioactive waste. Accordingly, since the metal sector of the CCIM contacts the high-temperature molten glass, cooling water is supplied to continuously cool the metal sector. The cooling system is divided into primary and secondary cooling water systems. The primary cooling water flows inside the metal sector of the CCIM to maintain the metal sector within normal temperature, thereby forming a glass layer between the metal sector and the high-temperature melting glass. The secondary cooling system is a system that cools the primary cooling water that cools the metal sector, and removes heat generated from the primary cooling system. In addition, it is designed to stably supply cooling water to the secondary cooling water system through an emergency cooling water system so that cooling water can be stably supplied to the secondary cooling water system in the event of secondary cooling water loss. Therefore, it is designed to maintain the facility stably in the event of loss of cooling water for the CCIM of the vitrification facility.

Bentonite, a material mainly used in buffer and backfill of the engineering barrier system (EBS) that makes up the deep geological repository, is a porous material, thus porewater could be contained in it. The porewater components will be changed through ‘water exchange’ with groundwater as time passes after emplacement of subsystems containing bentonite in the repository. ‘Water exchange’ is a phenomenon in which porewater and groundwater components are exchanged in the process of groundwater inflow into bentonite, which affects swelling property and radionuclide sorption of bentonite. Therefore, it is necessary to assess conformity with the performance target and safety function for bentonite. Accordingly, we reviewed how to handle the ‘water exchange’ phenomenon in the performance assessment conducted as part of the operating license application for the deep geological repository in Finland, and suggested studies and/or data required for the performance assessment of the domestic disposal facility on the basis of the results. In the previous assessment in Finland, after dividing the disposal site into a number of areas, reference and bounding groundwaters were defined considering various parameters by depth and climate change (i.e. phase). Subsequently, after defining reference and bounding porewaters in consideration of water exchange with porewater for each groundwater type, the swelling and radionuclides sorption of bentonite were assessed through analyzing components of the reference porewater. From the Finnish case, it is confirmed that the following are important from the perspective of water exchange: (a) definition of reference porewater, and (b) variations in cation concentration and cation exchange capacity (CEC) in porewater. For applying items above to the domestic disposal facility, the site-specific parameters should be reflected for the following: structure of the bedrock, groundwater composition, and initial components of bentonite selected. In addition, studies on the following should be required for identifying properties of the domestic disposal site: (1) variations in groundwater composition by subsurface depth, (2) variations in groundwater properties by time frame, and (3) investigation on the bedrock structure, and (4) survey on initial composition of porewater in selected bentonite The results of this study are presumed to be directly applied to the design and performance assessment for buffer and backfill materials, which are important components that make up the domestic disposal facility, given the site-specific data.

Owing to the increase in saturation rate of the spent fuel storage pond in the Kori nuclear power plant, the interim spent fuel dry storage facility is scheduled to be constructed at the Kori site. To implement safeguards in the new dry storage facility effectively, the concept of “Safeguards-by- Design” (SBD) should be applied to reflect nuclear safeguard provisions in the earliest design stages. Detailed design information pertaining to dry storage facilities has not been determined; however, the design information related to safeguards have been inferred using case studies and interviews with nuclear power plant operators worldwide. On the basis of the results of the case studies on spent fuel dry storage facilities for light water reactors, most countries apply the metal cask method in containment buildings considering safety. Furthermore, Korean operators are also considering the same method owing to tight licensing schedules and safety issues. Using the Facility Safeguardability Assessment (FSA) methodology (one of the safeguard evaluation methodologies), the difference in design between the heavy water reactor spent fuel dry storage facility, an established IAEA safeguards approach reference nuclear facility, and the light water reactor spent fuel dry storage facility (the new nuclear facility) were analyzed. Two major differences were noted as issues pertaining to potential safeguards. First, the difference in design and transport method in terms of the difference in size and weight of the spent nuclear fuel is important; light water reactor fuel is 20 times heavier than heavy water reactor that needs partial defect inspection in assemblies. Second, the difference in safeguard approach owing to the difference between the modular storage method in heavy water reactor and the container type storage method in light water reactor must be considered; movable storage cask renders the IAEA surveillance approach difficult. The results of this study can be used to identify the safeguards requirements in advance, enabling the operator to design new dry storage facilities resulting in timely and cost-effective implementation.

본 연구는 국내 수상스포츠 시설의 서비스스케이프가 고객만족 및 참여행동에 어떠한 영향을 미치는지를 규명하여 운영방안의 기초자료를 제공하고자 했다. 따라서 수상스포츠 시설을 경험한 사람들 중 20대 이상 참여자를 표본으로 선정했다. 조사는 2022년 4월 25일부터 7월 15일까지 비대면으로 실시했 으며, 총 243부의 데이터를 최종 분석에 이용했다. 자료처리는 SPSS(ver. 21.0) 프로그램을 활용해 빈도분 석, 탐색적 요인분석, 문항내적일관성, 상관분석, 단순 및 다중회귀 분석을 실시했다. 본 연구의 주요 결과, 첫째, 수상스포츠 시설 서비스스케이프가 편리성, 공감성, 시설환경 순으로 가치에 영향을 미치는 것으로 나타났다. 둘쨰, 수상스포츠 시설 고객만족이 참여행동에 영향을 미치는 것으로 나타났다. 셋째, 수상스포 츠 시설 서비스스케이프가 시설환경, 서비스, 편의성, 공감성 순으로 참여행동에 영향을 미치는 것으로 나 타났다.

A real scale leakage test facility was developed to study the leak signal characteristics of water supply pipelines, and then leak tests were carried out. The facility was designed to overcome the limited experimental circumstances of domestic water supply pipeline experimental facilities. The length of the pipeline, which was installed as a straight line, is 280m. Six pipes were installed on a 70m interval with different pipe material and diameters that are DCIP(D200, D150, D100, D80), PE(D75) and PVC(D75).The intensity of the leakage is adjusted by changing the size of the leak hole and the opening rate of ball valve. Various pressure conditions were simulated using a pressure reducing valve.To minimize external noise sources which, deteriorate the quality of measured leak signal, the facility was built at a quiet area, where traffic and water consumption by customers is relatively rare. In addition, the usage of electric equipment was minimized to block out noise and the facility was operated using manual mode. From the experimental results of measured leakage signal at the facility, it was found that the signal intensity weakened and the signal of high frequency band attenuated as the distance from the water leakage point increased.

Recently, the need for asset management(AM) plan introduction to reduce increasing O&M cost with aging water facilities is on the rise. Therefore, asset inventory classification is necessary as the first step for AM plan construction. In this study, all assets of YW water treatment plant(WTP) were classified as 5 steps. In addition, specific code name was given to each asset which can increase compatibility in constructing the AM programs among WTPs. In the future, codes for attribute and status of asset will be allocated, which can facilitate proper AM operation.

Pollutants removal efficiency in pretreatment(GAC filter, multi-media filter, disk filter) and RO facilities was investigated for the Jeju Samyang spring water source where raw water intake has been stopped due to sea water intrusion. In addition, preliminary feasibility analysis was conducted between RO and groundwater intake systems. Turbidity removal in 4 different pretreatment processes was less than 25% due to low concentration of turbidity(i.e., less than 0.21 NTU), while multi-media filter is recommended for the pretreatment facility based on the low organic content in raw water as well as cheaper operation and maintenance cost. The average concentration of Cl- in raw water was 691.4 mg/L, while that of RO permeate was 9.1 mg/L(i.e., removal efficiency was 98.4%). In addition, TDS removal efficiency was 98.1%, which was quite high. The production cost for RO system(Q=4,000 m3/d) was 362.1 won/m3 considering installation, operation and maintenance cost for 30 years. While that of groundwater was 262.6 won/m3 which was low compared to the RO system. However, it is recommended to introduce RO system for Samyang water source rather than new groundwater development because Samyang water source has been discharged to the sea without any usage, while groundwater can be used for other purpose as a sustainable water source.

본 연구에서는 막여과공정, 오존접촉공정, 활성탄흡착공정, 자외선소독공정 등이 계층형으로 배치된 정수처리 실증시설의 설계 및 운영을 통해 수직형 정수 처리시설의 최적 설계/운영방안을 도출하고자 하였다.

본 연구는 관로내의 민물담치 및 유생의 생물량을 효 과적 조절하기 위해서 수행되었다. 부착방지 및 생물량 조절방법은 기존에 사용되고 있는 염소처리법이 추천될 수 있었다. 민물담치의 산란기간은 수온 16~17􀆆C 범위 에 해당하는 5월~11월 초순 동안으로 추정되었다. 유생 을 조절하기 위해서는 이 기간에 염소처리를 하는 것이 적합하나, 기존에 부착하고 있는 치패와 성패가 동시에 고려되어야 하므로 연중 지속적으로 이루어져야 할 것 으로 판단된다. 산란이 시작되는 시기에서 각이 형성되 기 전인 유생기와 성패의 생물량 조절을 위해 0.5~1.0 ppm 범위의 염소농도로 처리하는 것이 적합하다. 민물 담치의 부착증식을 경감 또는 해결하기 위해서는 우선 적으로 국내 실정에 적합한 기술의 선정이 시급하였다. 또한 수온과 유생의 모니터링이 지속적으로 이루어져야 할 것으로 판단되며 유생 모니터링 방법 구축 및 염소 처리 효과분석에 대한 사후모니터링이 필요한 것으로 사료되어진다.

Korea's protected horticulture is rapidly increasing in scale due to various advantages such as year-round harvesting, labor savings through automation and shortened culture period, and greater income generation. This study was conducted to investigate the impact of protected horticulture on water quality. The results of this study are expected to provide basic data contributing to improvements towards sustainable agriculture and eco-friendly design of protected horticulture complex. The average T-N and T-P loads from vinyl greenhouses were 286.55± 143.98 mg/L and 59.14±13.77 mg/L, respectively and those from glass greenhouses 380.68 ± 150.41 mg/L and 61.85±20.72 mg/L. The annual discharge of wastewater derived from the monthly discharge from the horticulture greenhouses were estimated at 2597 ton/ha, with the annual phosphorus load amounting to 155.3 kg/ha. The average T-N and T-P loads in the tested greenhouse effluents were in excess of 8.3- and 13.5-fold the standards for the Korean wastewater plant effluent. The waste nutrient solution discharged from a protected horticulture complex can cause water contamination. Therefore, there is a need to conduct follow-up research using a water purification system or a trench method to develop a eco-friendly protected horticulture complex for sustainable agriculture.

This study proposes a selection method of a performance evaluation index of waterproofing and anti corrosion materials used in domestic water treatment facilities for material and construction failures based on different usage and environmental conditions to study the possibility of structural performance maintenance. Different types of waterproofing･anti-corrosion materials have been evaluated based on their respective properties, and have been classified into separate categories based on their case studies of material failures in construction. As a result, 12 different performance evaluation indexes have been produced for the performance evaluation method. Among the 12 performance evaluation index 5 were selected with relatively low importance that produced a low value of 60% importance using AHP analysis method, and conclusively proposed 7 performance evaluation index criteria (wet surface adhesion, fatigue resistance, crack resistance, adhesion performance, joint performance, impact resistance, impermeability)

A new array was suggested for effective leakage detection of concrete water facility. This array was modified to serve the purpose. Plus and minus currents have been installed respectively on the upstream and downstream water in order to detect the flow of water floating through the crack of facility. Potential poles in two lines have been installed closer than current sources to the weir to measure potential difference in upstream and downstream. Interpreting the potential difference data acquired by the new array, we could predict that where is the leakage zone. The possibility that can distinguish the leakage zone has been confirmed by numerical and physical modeling and problem position expected to leak was verified in field exploration.