Sustainable and healthy diet is a challenge in recent world. Despite the global depletion of water resources, Korea has no system for controlling its water footprint. This study established the water footprint tables of Korean food using the Water Footprint Network databases, and applied them into two meal plans for 19~64 year-old adults recommended in the Dietary Reference Intakes for Koreans 2020. Nut, oil, and meat’s water footprints were higher and those of fruit and vegetable were lower. Sesame oil had the highest water footprint of 21,793 L/kg and pineapple had the lowest domestic water footprint of 102 L/kg. Water footprint of one serving size of beef was 925 L, that of chicken was 260 L, and those of soybean were 43 L in global and 81 L in domestic. The water footprint of the recommended 2,400 kcal meal plan was 2,882 L, and that of 1,900 kcal meal plan was 1,915 L. The water resources can be saved by choosing food with lower water footprint. The results of this study can be used in the further researches for more sustainable and healthier Korean diet.

In this study, scones were prepared using Cordyceps powder, described as ‘immortal life’. Cordyceps powder was prepared in 0%, 2%, 4%, 6%, and 8% ratios, and salinity, color, texture, and antioxidant properties were analyzed. The salinity of Cordyceps scones did not show a difference according to the amount of Cordyceps powder added (p=0.364), and the a-, b-values increased significantly (p<0.001). In the case of texture, there was no significant difference in the amount of Cordyceps added. Flavonoids increased significantly as the amount of Cordyceps powder increased (p<0.001). ABTS-radical scavenging capacity increased significantly as the amount of Cordyceps powder increased (p<0.001). Through this study, the antioxidant properties of Cordyceps scones were confirmed.

In this research, KPS manufactured Full System Decontamination (FSD) equipment, which is consisted of Oxidizing Agent Manufacturing System (OAMS), Chemical Injection System (CIS), RadWaste Treatment System (RWTS), Chemical Waste Decomposition & Treatment System (CWDS) and conducted demonstration test to prepare Decontamination and Decommissioning (D&D) project of Kori nuclear power plant in Korea. Each equipment of FSD was modularized due to the limited size of equipment hatch of Kori nuclear power plant. To simulate the expected circumstances in nuclear power plant such as usage of heater or position of each equipment, additional equipment was used. The chemical concentration and flow rate of process water for FSD were used as mentioned in the previous study by KHNP CRI. FSD was conducted for three cycles and each cycle was consisted of oxidation, reduction, chemical decomposition and purification. Oxidation and reduction process were conducted at 90°C. Chemical decomposition and purification process were conducted at 40°C due to the damage of UV lamp and IX by the heat. Total volume of process water for FSD demonstration test was 2.5 m2. KPS conducted decontamination performance review by calculating thickness reduction and weight loss of installed specimen. Operational review was conducted as if FSD test was conducted in the field based on the result of demonstration test. One of the most prioritized features is the workers’ safety. Also, the appropriate position of equipment needs to be considered to meet the required specification of component.

CYPRUS is a web-based waste disposal research comprehensive information management program developed by the Korea Atomic Energy Research Institute over three years from 2004. This program is stored as existing quality assurance documents and data, and the research results can be viewed at any time. In addition, it helps to perform all series of tasks related to the safety evaluation study of the repository in accordance with the quality assurance system. In the future, it is necessary to improve the user convenience by clarifying the relationship between FEP and scenarios and upgrading output functions such as visualization and automatic report generation. This purpose of this study is to research and develop the advanced program of CYPRUS. This study is based on building FEP, DIM and scenario databases. It is necessary to develop an algorithm to analyze and visualize the FEP, DIM and scenario relationship. This project is an integrated information processing platform for DB management and visualization considering user convenience. The first development goal is to build long-term evolutionary FEP, DIM, and scenarios as a database. The linkage by FEP item was designed in consideration of convenience by using a mixed delimiter of letters and numbers. This design provides information on detailed interactions and impacts between FEP items. Scenario data lists a series of events and characteristic change information for performance evaluation in chronological order. In addition, it includes information on FEP occurrence and mutual nutrition by period, and information on whether or not the repository performance is satisfied by item. The second development goal is to realize the relationship analysis and visualization function of FEP and scenario based on network analysis technique. Based on DIM, this function analyzes and visualizes interactions between FEPs in the same way as PID, RES, etc. In addition, this function analyzes FEP and DIM using network analysis technique and visualizes it as a diagram. The developed platform will be used to construct and visualize the FEP DB covering research results in various disposal research fields, to analyze and visualize the relationship between core FEP and scenarios, and finally to construct scenarios and calculation cases that are the evaluation target of the comprehensive performance evaluation model. In addition, it is expected to support the knowledge exchange of experts based on the FEP and scenario integrated information processing platform, and to utilize the platform itself as a part of the knowledge transfer system for knowledge preservation.

In Korea, borated stainless steel (BSS) is used as spent fuel pool (SFP) storage rack to maintain nuclear criticality of spent fuels. As number of nuclear power plants and corresponding number of spent fuels increased, density in SFP storage rack also increased. In this regard, maintain subcriticality of spent nuclear fuels was raised as an issue and BSS was selected as structural material and neutron absorber for high density storage rack. Because it is difficult to replace storage rack, corrosion resistance and neutron absorbency are required for long period. BSS is based on stainless steel 304 and it is specified in the ASTM A887-89 standard depending on the boron concentration from 304B (0.20-0.29% B) to 304B7 (1.75-2.25% B). Due to low solubility of boron in austenitic stainless steel, metallic borides such as (Fe, Cr)2B are formed as secondary phase metallic borides could make Cr depletion near it which could decrease the corrosion resistance of material. In this paper, long-term corrosion behavior of BSS and its oxide microstructures are investigated through accelerated corrosion experiment in simulated SFP condition. Because corrosion rate of austenitic stainless steel is known to be dependent on the Arrhenius equation, a function of temperature, corrosion experiment is conducted by increasing the experimental temperature. Detail microstructural analysis was conducted with scanning electron microscope, transmission electron microscope and energy dispersive spectrometer. After oxidation, hematite structure oxide film is formed and pitting corrosions occur on the surface of specimens. Most of pitting corrosions are found at the substrate surface because corrosion resistance of substrate, which has low Cr content, is relatively low. Also, oxidation reaction of B in the secondary phase has the lowest Gibbs free energy compared to other elements. Furthermore, oxidation of Cr has low Gibbs free energy which means that oxidation of B and Cr could be faster than other elements. Thus, the long-term corrosion might affect to boron content and the neutron absorption ability of the material.

For safe management of spent nuclear fuels, they should be delivered to repository or waste disposal site. As the amount of spent nuclear fuel transportation is expected to increase in the future due to the provision of an intermediate storage facility, the necessity to secure transportation cask is emerging. In order to secure the spent nuclear fuel transportation cask, it is necessary to analyze the regulatory processes for domestic and foreign spent nuclear fuel transportation cask. In this study, the regulatory processes for domestic and foreign spent nuclear fuel transportation cask was analyzed. In this study, the IAEA, US, and Korea spent nuclear fuel transportation cask regulatory processes were analyzed. The domestic and foreign spent nuclear fuel transportation cask regulatory processes consist of design phase, manufacturing phase, and operation phase. In the design stage, the transport requirements are designed in accordance with the safety requirements of international organizations and countries. The application to be submitted when applying for approval should include a safety analysis report, evidence proving compliance with safety requirements et al. In the manufacturing stage, it is a stage to check whether the safety requirements are satisfied before the first use after manufacturing the transportation cask. Inspections include welding inspection, leakage inspection, shielding inspection, and thermal inspection. In the operation stage, it is a stage of periodically performing inspections for continuous maintenance of the package when the transportation cask is used. The inspection items to be performed are similar to the manufacturing stage and typically include performance inspection of components and leakage inspection. In this study, domestic and foreign spent nuclear fuel transportation cask regulatory processes were analyzed. It was found that the domestic and foreign spent nuclear fuel transportation cask regulatory processes consist of the design phase, the manufacturing phase, and the operation phase. The results of this study can be used as basic data for policy decision-making for the spent nuclear fuel cask.

게임플레이는 플레이어가 게임과 상호작용을 진행하면서 게임 상황에 대한 판단과 행동의 일련의 과정의 반복이라고 볼 수 있다. 잘 설계된 게임플레이는 플레이어로 하여금 게임에 몰입하도록 유도하며, 지속적으 로 몰입상태를 유지할 수 있도록 한다. RPG에서 게임플레이의 핵심과정중 하나는 몬스터와 상호작용하는 것이다. 일반적인 RPG의 몬스터는 패턴플레이로 구성되어 반복적으로 플레이가 진행되는 상황에서 지루함 을 유발하는 요인으로 작용한다. 이로 인해 게임을 플레이하는 플레이어중 고 레벨 플레이어는 레벨업을 위 해 습득해야 하는 경험치의 양의 증가로 인해 같은 필드에서 같은 몬스터를 오랜 시간동안 플레이하는 것 이 일반적이어서 시간이 지날수록 투자한 시간과 성취욕구 사이에서 만족도가 떨어지는 문제점이 발생한다. 본 연구에서는 플레이어의 성장과정에서 몬스터가 제공하는 정보에 대한 위계의 설정을 통하여 플레이어의 인지과정에 패턴의 변수를 인식하게 하여 다양한 게임플레이가 가능하도록 하며 이를 바탕으로 플로우 (Flow) 과정에서 경험하는 지루함의 요소를 극복하고 지속적으로 몰입과정을 느낄 수 있도록 한다.

The effect of oxidation time on the characteristics and mechanical properties of spent nuclear fuel cladding was investigated using Raman spectroscopy, tube rupture test, and tensile test. As oxidation time increased, the Raman peak associated with the tetragonal zirconium oxide phase diminished and merged with the Raman peak associated with the monoclinic zirconium oxide phase near 333 cm−1. Additionally, the other tetragonal zirconium oxide phase peak at 380 cm−1 decreased after 100 d of oxidation, whereas the zirconium monoclinic oxide peak became the dominant peak. The oxidation time had no effect on the tube rupture pressure of the oxidized zirconium alloy tube. However, the yield and tensile stresses of the oxidized nuclear fuel cladding tube decreased after 100 d of oxidation. The results of the scanning electron microscopy and transmission electron microscopy were represented with the in-situ Raman analysis result for the oxide characteristics generated on the cladding of spent nuclear fuel.

Domain decomposition method (DDM) has been widely employed for the numerical analysis of large-scale problems due to its applicability to parallel computing. DDM divides the modeling domain into a set of subdomains and obtains the entire solution iteratively until the values of each subdomain which are shared with other subdomains, such as boundary values, are converged. Therefore, in general, DDM is a memory-efficient iterative algorithm with inherent parallelism on the geometric level. APro, the process-based total system performance assessment model, aims for simulating the radionuclide transport considering coupled multi-physics phenomena occurring in large-scale geological disposal system, which are inevitably accompanied by huge memory burden. Therefore, DDM is applicable for the large-scale problem of APro and its performance in parallel computing needs to be examined. The DDM solvers provided by COMSOL which constitute APro can be classified into two methods. One is the overlapping Schwarz method that each subdomain overlaps its neighboring domains and the other is the Schur complement method that subdomains are non-overlapping and separated by boundary domains. For the Schwarz method, the additive, hybrid, multiplicative and symmetric methods can be selected according to the solution update scheme. And for the Schur method, the additive and multiplicative ordering options can be chosen for solving Schur complement system. In this study, the calculation efficiency of the DDM solvers in COMSOL and the applicability to the cluster environment were examined. In aspect of efficiency, the memory requirements with different number of subdomains and calculation schemes were compared in a single node. Then, the memory requirements with increasing number of disposal tunnels and deposition holes were investigated in multiple nodes. As a result, on the cluster environment, with the help of distributed memory architecture which enables efficient memory usage, the applicability of DDM solvers to the large-scale problem of APro was confirmed.

Non-destructive estimation of leaf area is a more efficient and convenient method than leaf excision. Thus, several models predicting leaf area have been developed for various horticultural crops. However, there are limited studies on estimating the leaf area of strawberry plants. In this study, we predicted the leaf areas via nonlinear regression analysis using the leaf lengths and widths of three-compound leaves in five domestic strawberry cultivars (‘Arihyang’, ‘Jukhyang’, ‘Keumsil’, ‘Maehyang’, and ‘Seollhyang’). The coefficient of determination (R2) between the actual and estimated leaf areas varied from 0.923 to 0.973. The R2 value varied for each cultivar; thus, leaf area estimation models must be developed for each cultivar. The leaf areas of the three cultivars ‘Jukhyang’, ‘Seolhyang’, and ‘Maehyang’ could be non-destructively predicted using the model developed in this study, as they had R2 values over 0.96. The cultivars ‘Arihyang’ and ‘Geumsil’ had slightly low R2 values, 0.938 and 0.923, respectively. The leaf area estimation model for each cultivar was coded in Python and is provided in this manuscript. The estimation models developed in this study could be used extensively in other strawberry-related studies.

최근에 캐릭터 커스터마이징 서비스가 다양하게 보편화된 이후 서비스마다 모두 다른 UI와 용어들이 혼재하고 있어서 사용자들의 불편함도 함께 증가하고 있다. 또한 갑작스럽게 늘어난 서비스에 비해서 아직 활용할 수 있는 연구 결과나 디자인 가이드가 마땅히 없으므로 새로운 서비스를 기획하거나 개발할 때 참고할 만한 자료가 부재 하다. 본 연구에서는 현 시점에서 캐릭터 커스터마이징 UI들이 어떻게 구성되어 있는지 상위 5개의 메타버스, 모 바일 게임, PC게임 서비스의 캐릭터 커스터마이징 시스템 UI를 조사하고 경향을 분석했다. 첫째, 커스터마이 징 항목의 수는 분포가 매우 다양했다. 얼굴의 이미지 형성에 큰 영향을 미치는 눈, 눈썹, 입, 그리고 상체의 조절 항목이 가장 세분화 되어 있었다. 둘째, 용어의 일관성이 떨어져 기능을 인지하기 어려운 점이 발견되 었다. 셋째, 커스터마이징 조절 도구의 위치를 조사한 결과, 세로형 메타버스에서는 상￿하단에, 가로형 PC와 모바일 게임에서는 좌우 배치 또는 유동형 배치로 구성되어 있었다. 넷째, 커스터마이징 조절 도구의 유형은 대분류에서는 선택형, 중분류에서는 선택형, 하위 단계에서 조절형으로 구성되었으며 일부 복합형도 있었다. 다섯째, 조절 수치의 범위 역시 일관성이 없고, 초기 값에 대한 상대적인 수치의 가감으로 조절하고 있어서 사용자들의 정확한 의사소통과 직관성을 위한 보완이 요구 되었다. 여섯째, 색상 선택 기능은 일부 항목에 한정되어 있었고, 시스템에 제안된 범위의 색을 선택하거나 색공간을 이용할 수 있었다. 패션 선호도와 트렌 드를 민감하게 반영하고 있는 점이 발견되었다.

프리지아 ‘Sunny Gold’는 농촌진흥청 국립원예특작과학원 에서 2010년 노랑색 반겹꽃 프리지아 육성계통 ‘036010’을 모본으로 진노란색 홑꽃 ‘Golden Flame’을 부본으로 교배하여 획득한 종자로부터 2011년 진노란색 겹꽃의 향기가 강한 프리지아 계통을 선발하여 품종화 하였다. 2011년부터 2016년까지 개화 생육특성검을 수행하였으며 핵심수요자의 기호도 평가를 통해 선발되어 2017년 ‘Sunny Gold’ 로 명명되었다. ‘Sunny Gold’는 RHS color chart YO17B의 노란색 겹꽃 프리지아 품종으로 화폭은 6.7cm로 대조품종 ‘Golden Flame’ 6.1cm에 비해 크고, 분지수는 6.5로 다수확성 품종이다. 초장이 101.9cm로 초세가 강하다. ‘Sunny Gold’의 소화수 및 소화장은 각각 13.0개, 9.3cm이며 개화소요일수는 137.7일이다. 이 품종의 절화수명은 약 9일이며 자구번식력은 5.3배로 대조 품종 ‘Golden Flame’ 4.3배에 비해 우수하다. 전자코를 이용한 PCA분석결과 PC1과 PC2는 각각 99.3%와 0.6%로 전체 변이량의 99.9%를 반영하고 있다. Rader plot 분석결과 총 6개 센서에서 모두 ‘Sunny Gold’의 센서값이 향기가 강한 상용품종 ‘Yvonne’의 값에 비해 높게 나타나 ‘Sunny Gold’의 향기가 더 강한 것으로 나타났다.