본 연구에서는 디지털 게임 내 성폭력 피해 경험과 가해 경험의 내용과 특성에 대해 탐색하고자 하였다. 성폭 력 피해/가해 경험의 구체적인 내용과 정도, 성폭력 경험으로 인한 정서적 영향, 성폭력 피해시의 대처양식 등 을 조사할 수 있는 질문지를 개발하여 20세 이상의 게임 사용자들을 대상으로 온라인 설문을 실시하였고, 총 267명의 자료가 분석되었다. 그 결과, 연구참여자의 99.3%가 1회 이상 성폭력 피해를 경험하였고, 성폭력 가해 도 연구참여자의 62.5%가 경험한 것으로 나타났다. 또한 성폭력 피해와 가해 모두에서 간접적 성희롱이 가장 높은 수준으로 경험되고 있었다. 피해 경험으로 인한 정서적 영향에 있어, 지속적인 성폭력 피해가 있는 경우, 피해자들은 분노/짜증, 우울/불안, 적대감/스트레스를 유의미하게 높게 경험하였다. 피해 경험 시 대처전략은 ‘게임 내 신고시스템에 신고’가 가장 높게 나타났고, 다음으로 부정과 회피가 뒤따랐다. 가해 경험으로 인한 정서적 영향의 경우, 가해 상위 10% 집단이 하위집단에 비해 가해 행동을 통해 스릴/흥분과 같은 심리적 자극 을 경험하는 동시에 죄책감 등의 부정적 정서도 높게 경험하는 것으로 나타났다. 성폭력 피해/가해 경험의 정 도를 기준으로 집단 간 차이를 비교한 결과, 게임 이용 행동에 있어 집단 간 차이가 있는 것으로 확인되었다. 본 연구는 특정 게임이 아닌 다양한 장르와 특성의 게임들에서 발생하는 성폭력의 내용과 정도 등의 구체적 인 실태를 파악했다는데 의의가 있다. 또한 해외 연구에서 사용된 연구 틀을 그대로 적용하지 않고, 우리나라 게임 사용자들의 디지털 게임 내 성폭력 경험에 대해 실제적으로 접근하였다는데 의의가 있다.

The potentiostatic titration method is one of the effective methods for determining the total uranium assay in high-concentration uranium samples. A notable approach is the Devies-Grey titration method, which was first reported in 1964. In the U sample treatment process of this method, the reduction of U(VI) by Fe(II) is initially a non-spontaneous reaction based on the reduction potentials of the two half-reactions. However, in a high-concentration phosphoric acid medium, the reduction potential of Fe(II) is enhanced, simultaneously increasing the reduction potential of U(VI). As a result, the redox reaction becomes spontaneous due to these dual effects. On the other hand, the reaction kinetics can elucidate why nitric acid does not oxidize U(IV) during the oxidation of Fe(II) to Fe(III). Furthermore, the role of Mo(VI)/Mo(V) as a redox enhancer, employed alongside nitric acid, can be comprehended through electrochemical means. Similarly, the function of V(IV) as an electrochemical enhancer, aiding the action of the Cr(VI) titrant, becomes understandable. Grasping the various phenomena that manifest during the titration process is imperative for refining existing titration methods and pioneering new ones.

When occurring at a nuclear power plant (NPP) by accidents, accurate prediction and identification of the process of radioactive material dispersing into atmosphere is important to protect public and environment. Atmosphere dispersion of radioactive materials is significantly influenced by wind direction and wind speed. The government and nuclear operator continuously monitor wind data at nuclear sites through meteorological tower to prepare for such accidents involving the release of radioactive materials. The purpose of this study is to construct wind rose diagrams at 5 NPP sites (Kori, Saewool, Wolsong, Hanbit, Hanul). Wind roses serve as invaluable tool for identifying wind patterns in each region and visualizing wind directions. This can be utilized to predict the dispersion pathway and extent range of radioactive materials carried by the wind. This program will take on the role of establishing appropriate evacuation routes or shelter locations for residents when reliable wind data is not immediately available during an NPP accident. The wind data used in the study was collected from a meteorological tower located at the NPP site, and measurements were taken at 1-hour intervals for each operation over a period of ten years. The collected data underwent preprocessing, followed by the development of Python code to render the wind rose diagrams in an interpretable format. The future direction of this study will be focused on enhancing this program by integrating geographical mapping capabilities. With these advancements, it will become feasible to superimpose shelter positions on a map in accordance with prevailing wind directions. These improvements will contribute to the development of additional protective measures for residents and the proposal of alternative shelter options in response to potential radioactive material releases.

In the case of nuclear projects, when developing a new reactor type, it is necessary to confirm the reactor type, secure the safety, and especially obtain the construction permit approval of the licensing authority for construction. Schedule management is necessary to carry out nuclear projects, and progress rate management of project progress management is largely composed of three elements: scope management, cost management, and resource management. However, in the case of the small modular reactor (SMR) project currently being carried out, it is difficult to calculate the progress rate including budget and resources due to the nature of the project. Therefore, in the SMR project, it took two years from the beginning to prepare the integrated project master schedule (IPMS) to prepare the draft, and then two revisions were made over a year and a half. In this SMR project, we will consider the entire construction period such as design, purchase and production, construction, commissioning, and operation in terms of scope management. The entire document list was created using the document review and approval sheet created at the beginning of the design. In the PMIS (Project Management Information System), the number of approved documents was calculated by comparing the list of engineering documents. In the purchase production part, the main core equipment such as the primary system nuclear steam supply system (NSSS), the secondary system turbine and condenser, and the man machine interface system (MMIS) are managed. Purchasing and manufacturing management shall be managed so that major equipment can be delivered in a timely manner in accordance with the schedule for delivery of equipment in the IPMS. In order to prevent delays in the start of production, it is necessary to minimize the waiting time for work through advance management tasks such as insurance of drawing, stocking of materials, availability of production facilities, etc. In this way, we decided to carry out the schedule management for the design, purchase and manufacturing part in the SMR project first, and the installation, construction and commissioning part will be prepared for the future schedule management.

마늘은 백합과 알리움속에 속하는 영양체작물로 누대재배시 수확량이 감소하는 특성을 보인다. 마늘의 화경 끝에는 주아가 생성되는데, 주아를 파종하여 2년이상 누대재배시 수확량이 약 15% 이상 증가하기 때문에 주아재 배를 통한 종구 갱신이 필요하다. 마늘 주아를 수확 후 저장시 파총채벌레, 파좀나방 등이 발생하며, 저장 중 주아 는 매년 평균 20% 이상의 부패한다. 주아재배를 원활히 하기 위해 주아 저장 시 해충의 방제를 통해 부패율을 줄이는 것이 중요하다. 본 연구에서 주아에서의 해충 발생밀도 및 방제방법에 대한 연구를 진행하였다. 연구결과 주아에서 파총채벌레는 7월 3주차, 파좀나방은 7월 2주차에 각각 발생최성기를 보였으며, 약제 침지시 방제가가 90% 이상 관찰되었다. 약제 침지된 주아 파종시 약해는 발생하지 않아, 주아 해충 방제시 침지법을 활용하여 해충의 밀도를 조절 할 수 있을 것으로 판단된다.

마늘은 백합과 알리움속에 속하는 작물로 약용, 양념채소로 많이 소비되어져 왔다. 마늘은 6월에 수확하여 1개월 간의 건조과정을 거치게 되는데 보통 장마기와 겹치게 되어 연평균 부패율은 5%이상으로 높다. 마늘의 저장중 병해충은 뿌리응애, 마늘혹응애, 마른썩음병 등으로 섭식에 따른 부패를 유발하며, 건조시기를 단축하고 효율적인 건조를 통하여 감모율을 줄이는 것이 중요하다. 마늘의 병해충 피해를 줄이기 위해 개발한 열풍 흡기식 건조장치를 포함하여 관행, 열풍 건조기, 흡기식 건조 등 4가지 방법으로 마늘을 건조하였으며, 방법별 건조소요 일수, 부패율 등을 조사하였다. 연구결과 열풍-흡기식 건조장치의 순환 공기의 온습도는 외기대비 7.8℃ 높았고, 28.6% 낮았으며, 건조 소요일수는 관행건조 대비 31% 수준으로 우수하였다. 또한 병해충 피해 양상은 관행 건조 대비 4.4%p낮아 건조 기간 및 정상품율이 관행 대비 우수하여, 관행 건조를 대체 가능할 것으로 생각된다.

주변 국가인 태국, 캄보디아, 베트남, 라오스 등에서 벼멸구(Nilaparvata lugens)와 흰등멸구(Sogatella furcifera)를 채집하던 중, 벼멸구와 형태가 아주 유사한 이삭멸구(N. muiri)와 벼멸구붙이(N. bakeri), 그리고 흰등 멸구와 형태가 아주 유사한 흰등멸구붙이(S. kolophon), 피멸구(S. vibix) 그리고 애멸구(Laodelphax striatellus)가 동시에 채집이 되는 등 형태적 차이점이 거의 없어 전문가도 쉽게 구분하지 못하는 문제가 있음이 확인되었다. 따라서 형태가 유사한 상기 멸구류의 종 동정을 확실히 할 수 있는 PCR용 프라이머의 개발을 위해 벼멸구 및 흰등멸구의 미토콘드리아 내 COI 영역을 특이적으로 검출할 수 있는 프라이머 세트를 제작하고 종 동정 효과를 확인하였다.

본 연구는 광질이 장미의 꽃잎 착색에 미치는 영향에 대한 기초자료를 얻고자 수행했다. 꽃눈 분화가 시작된 미니 장미 5품종 ‘Berigamo’(yellowish white), ‘Elpaso Yellow’(yellow), ‘Elpaso’ (bicolor, yellow+orange), ‘Meggiore’(pink), ‘Maasland’(red)를 대상으로 3주간 광질처리를 실시하였다. 광질처리는 300μmol·m-2·s-1 백 색광(W) 대조구와 210μmol·m-2·s-1 백색광에 적색(R), 녹색(G), 청색(B), 원적외선(FR) 및 자외선 B(UVB)을 각 90μmol·m-2·s-1 보광하여 대조구와 동일한 PPFD로 설정하였다. 광질의 꽃잎착색 효과는 품종 특이적으로 R, FR, UVB 보광은 특히 분홍색 품종에서 각각 19.0%, 28.8%, 6.4% 착색을 증진시킨 반면, G와 B 보광은 안토시아닌 함량을 각각 17.8%, 19.0% 감소시켰 다. 황색 품종에서는 UVB보광으로 카로티노이드 함량이 19.6% 증가하였다.

우리나라 정원 트렌드를 분석하기 위해 국내 활동 디자이 너를 대상으로 설문을 통해 조성 경력, 디자인 양식, 식재 이 용성, 정원 소재 선호도를 분석하였다. 최근 5년 활동 경력 보유 디자이너는 연 평균 1~4개소의 정원을 조성하며, 주로 공모전 및 초청 전시와 기업 및 공공기관 정원 조성에 참여 하고 있다. 정원 조성 시, 주변 생태, 경관 및 식재의 조화를 고려하여 주로 비정형식 디자인을 선호한다. 정원 내부 설치 구조물 보다는 식재 활용성이 약 74%, 교목 및 관목보다는 초본류 식재율이 약 39~55% 더 높은 것으로 확인하였다. 국 내 디자이너는 정원 내 교목, 관목, 초본류의 식재 비율을 평 균 2:5:9로 설정하며 저관리성 소재인 사초 및 양치류의 선 호도가 높은 것으로 나타났다. 식재 밀도의 경우, 정원 이용 목적 및 디자인에 따라 상이하지만 100m2 기준 평균 11~40 종을 활용하여 약 1,000~3,000본/주를 식재하는 것으로 조 사되었다.

Measurement of oxide ion (O2-) concentration is a basic technology required in molten salt fields, from energy storage systems to electrolytic reduction of rare earth elements or spent nuclear fuels. In a molten salt reactor, O2- ions react with actinide elements to form their oxides or oxy-chlorides to induce actinide precipitation, and promote metal corrosion to cause a failure of structural material. For these reasons, removal of O2- ions and monitoring of the O2- concentration in molten salt reactors are essential. In this study, methods using chemical and electrochemical methods were investigated for measuring the concentration of O2- ions in a molten salts. The acid-base neutralization reaction was used as a chemical analysis method. And electrochemical methods using the O2- diffusion limit current and YSZ (yttria stabilized zirconia) indicator electrode were used for measuring the O2- concentration. Finally, a modified method using porous membrane electrode was applied to monitor the O2- concentration. The O2- concentration was measured up to about 2wt% of Li2O by the method using the O2- diffusion current, up to about 4wt% by the YSZ indicator electrode, and about 6wt% by the porous membrane electrode in LiCl molten salts.

Natural radionuclides-containing substances (NORM) contain natural radionuclides and cause radiation exposure. In Korea, safety management measures were needed to deal with and dispose of radon mattresses containing monazite in relation to such NORM. However, there is no clear safety management system related to NORM waste in Korea. In order to manage this reasonably and systematically, it is necessary to investigate and analyze standards and management measures related to the treatment and disposal of NORM waste. Therefore, this study investigated and analyzed the exemption and clearance level of NORM waste regulations in international organizations and foreign countries. IAEA GSR Part 3, 2013/59/Euratom, ANSI/HPS N13.53, CRCPD SSRCR Part N, and ARPANSA Publications 15 safety management regulations were analyzed to investigate safety management standards for NORM waste. The exemption and clearance level in international organizations and foreign countries were compared and analyzed based on radioactive concentration and dose. In addition, the management measures proposed for each literature were also investigated. As a result of the analysis, IAEA GSR Part 3 applied 1 mSv as a regulatory exemption level, 1 Bq/g for uranium and thorium series as a clearance level, and 10 Bq/g for K-40 nuclides. The IAEA recommends a differential approach to the potential and scale of exposure. The EU applied 1 Bq/g to uranium and thorium families and 10 Bq/g to K-40 nuclides for both regulatory exemption and clearance levels. The EU recommended that it be managed in proportion to the scale and likelihood of exposure as a result of the action. It is analyzed that this is similar to the IAEA’s management plan. In the United States, there was no single federal government radioactive concentration and dose for NORM management. The management plan differed in management status and level from state to state, and K-40 was excluded from regulation unless it was intentionally enriched. In the case of Australia, the radioactive concentration of uranium and thorium was 1 Bq/g as a standard for regulatory exemption and 1 mSv as a dose. As a management plan, it was suggested to dispose of waste by means of accumulation, dilution/dispersion, and reclamation. It was also suggested that the scale of exposure, like international organizations, take into account the possibility. The results of this study are believed to be used as basic data for presenting domestic NORM waste treatment and disposal methods in the future.

In the event of a radioactive release, it is essential to quickly detect and locate the source of the release, as well as track the movement of the plume to assess the potential impact on public health and safety. Fixed monitoring posts are limited in their ability to provide a complete picture of the radiation distribution, and the information they provide may not be available in real-time. This is why other types of monitoring systems, such as mobile monitoring, aerial monitoring, and personal dosimeters, are also used in emergency situations to complement the information provided by fixed monitoring posts. Also, the monitoring system can be improved by using the Kriging technique, which is one of the interpolation methods, to predict the radiation dose in the relevant districts. This can be achieved by utilizing both the GPS information and the radiation dose measured at a particular point. The Kriging method involves estimating the value between different measurement points by considering the distance between them. The model used GPS and radiation data that were measured around the Hanbit NPP. The data were collected using a radiation measuring detector on a bus that traveled around the NPP area at 2-second intervals for one day. From the collected data, 200 data points were randomly selected for analysis, excluding the data measured at the bus garage out of a total of 16,550 data points. The average dose of the daily measurement data was 117.94 nSv/h, and the average dose of the 200 randomly extracted data was 119.17 nSv/h. The GPS and radiation dose data were utilized to predict the radiation dose around the Yeonggwang area where the Hanbit NPP is located. In the event of an abnormal release of radioactive material, it can be difficult to accurately determine the dose unless a monitoring measurement point is present. This can delay the rapid evacuation of residents during an emergency situation. By utilizing the Kriging model to make predictions, it is anticipated that more accurate dose predictions can be generated, particularly during accident scenarios. This can aid in the development of appropriate resident protection measures.