목적: 본 연구는 독거노인을 위한 건강증진 중재 방법 중 신체적 건강, 정신적 건강, 사회적 건강 모두 긍정적인 영향을 미치는 중재 유형 및 방법을 알아보고자 한다. 연구방법: 분석 대상 논문 추출은 PubMed, Embase, Research Information Sharing Service, DBPia의 데이터베이스를 사용하였다. 검색 기간은 2013년 1월부터 2023년 1월까지 설정했다. 검색어는 (“elderly” OR “older” OR “old adult” OR “age”) AND (“health promotion” OR “health improve”) AND (“living alone” OR “live alone”) AND “intervention”으로 하였다. 결과: 최종분석 대상 연구의 질적 수준은 무작위 배정 연구 4편, 실험-대조군 연구 2편이었다. 총 6편의 건강증진 중재의 유형은 가정 방문 2편, 전화와 가정 방문 병행한 연구 2편, 전화 1편, 기관 방문 1편이었다. 연구 결과에 따르면 가정 방문 중재는 대조군과 비교하여 악력을 제외한 신체적 건강, 정신적 건강, 사회적 건강에 대한 유의한 차이를 나타냈다. 결론: 독거노인을 위한 건강증진 중재는 가정 방문 중재 유형이 건강관리 교육, 운동 및 인지 프로그램을 통해 다른 중재 유형보다 신체적, 정신적 건강에 미치는 긍정적인 효과성을 확인하였다. 독거노인의 건강증진 측면에서 관련 중재 이점을 인식하고 효과성을 극대화하기 위한 전략 마련과 적용에 대한 추가 연구가 필요하다.

목적: 본 연구는 독거노인을 대상으로 한 사회적 고립 중재를 살펴보고 그 효과성을 알아보고자 하는 것에 목적이 있다. 연구방법: 2012년 1월부터 2023년 1월까지 SCOPUS, Web of Science, Research Information Sharing Service, CINAHL을 데이터베이스로 이용하여 검색하였고, 주요 검색용어로는 “social isolation” AND (“older” OR “elder” OR “aged” OR “geriatric”) AND (“living alone” OR “live alone”) AND “intervention” 을 사용하였다. 최종적으로 선정된 5편의 연구를 분석하였다. 결과: 선정된 5편의 연구 중 4편의 연구에서 사회적 상호작용과 관련된 중재를 제공하였고, 나머지 1편의 경우 컴퓨터 기반 중재를 제공하였다. 중재를 시행한 결과, 사회적 고립과 외로움 감소에 효과적인 것으로 나타났고, 그 외에도 사회적 지지, 환경적 삶의 질, 삶의 만족도, 기술적 소양, 웰빙, 그리고 사람과 공공 사회 보장에 대한 신뢰 향상의 효과가 있었다. 결론: 본 연구를 통하여 사회적 고립을 호소하는 독거노인을 대상으로 한 중재에 대해 알아보았다. 이는 작업치료 현장에서 독거노인의 사회적 고립 중재가 효과적으로 이루어지기 위한 기초 자료로 활용될 수 있을 것이다.

목적: 본 연구는 작업치료사가 시행한 시간 관련 중재의 효과와 임상 적용에 관하여 체계적으로 분석하였다. 연구방법: 2000년 1월부터 2022년 12월까지 학술연구정보서비스(Research Information Sharing Service), DBpia, PubMed, EMBASE, Web of Science 및 CINAHL을 통해서 ‘장애’, ‘시간관리’, ‘시간보조도구’, ‘중재’, ‘프로그램’, ‘작업치료’를 검색하였다. 해당 문헌들은 PRISMA-2020에 따라 체계적인 검토를 수행하였 고, PEDro를 통하여 연구의 질적 평가를 실시하였다. 최종 선정 기준에 부합한 연구는 총 9편이었다. 결과: 선정된 9편의 시간 관련 중재 중 시간기술훈련과 시간보조도구를 혼합하여 사용한 논문은 4편(44.5%), 시간보조도구는 3편(33.3%), 시간기술훈련은 2편(22.2%)이었다. 시간 관련 중재를 적용한 결과 시간기술에서 유의미한 효과를 보였다. 또한 인지 및 일상생활 기능, 작업 수행도 및 만족도, 심리 사회적 요인의 향상이 나타났다. 결론: 본 연구는 시간 관련 중재가 클라이언트의 시간 처리 능력 및 일상생활 수행 및 삶의 질 영역에 긍정적인 효과를 확인하였다. 추후 국내 작업치료 분야에서도 다양한 시간 관련 중재가 활용되기를 기대한다.

Syntax-semantics mismatch refers to a phenomenon whereby a part of a sentence appears to be attributive in form, but is in fact semantically matched with other syntactic components. Throughout previous research on the phenomenon of syntax-semantics mismatch, there has been a certain consensus in the academic community on some issues. It is believed that the syntax-semantics mismatch structure can be mainly divided into two types: pseudo possession and pseudo nominal quantity. The syntax-semantics mismatch structure is not a prototype structure, but a transformation from a certain prototype structure. The NP2 in the syntax-semantics mismatch structure is an undirected component. In addition, there are still some issues in the academic community that have not reached consensus. Different scholars have different opinions on the issue of whether there is a possessive relationship within the syntax-semantics mismatch structure (pseudo possessive). Some scholars believe that there is no possessive relationship between NP1 and NP2 within the form meaning mismatch structure, while others hold the opposite view. In terms of the mechanism of the formation of the syntax-semantics mismatch structures, different scholars have different research perspectives, and scholars with the same research perspective also have specific differences in their viewpoints. The article reviews previous research from three aspects: the qualitative nature of the syntax-semantics mismatch structure, the semantic characteristics of the syntax-semantics mismatch structure, and the generation mechanism of the syntax-semantics mismatch structure. It also briefly summarizes the existing problems in current research.

목적: 본 연구는 자폐 스펙트럼 장애 아동을 대상으로 DIR/FLOORTIME 중재의 효과, 종속변수 및 프로토콜을 확인하는 것을 목적으로 하였다. 연구방법: Cumulative Index of Nursing and Allied Health Literature, Excrepta Media Database, MEDLINE 및 Google Scholar를 데이터베이스로 사용하여 수집하였다. 연구는 체계적 연구 및 메타 분석 흐름도를 위한 선호도 항목에 따라 선택되었다. 최종적으로 11개의 연구가 최종 분석에 포함되었고, 선택된 연구들은 Arbesman 등(2008)이 제시한 증거 기반 연구의 질적 수준 모델을 사용하여 평가되었다. 결과: 4편의 무작위 대조군 연구가 Level I에 해당된 것으로 미루어보아 DIR/FLOORTIME에 대한 근거 수준이 높은 편이었다. DIR/FLOORTIME 중재의 종속변수는 의사소통 및 정서, 부모 스트레스, 자폐성 중증도, 감각처리, 발달 이정표, 인지, 언어, 놀이 순이었으며 모든 연구에서 유의미한 결과가 도출되었다. 결론: 본 연구는 자폐스펙트럼장애 아동을 대상으로 DIR/FLOORTIME 중재기법의 적용애 대한 문헌들을 연구하였으며, 향후 자폐스펙트럼 장애 아동들을 대상으로 DIR/FLOORTIME 중재를 활용하기 위한 전략과 프로토콜의 근거를 제시하고자 한다.

목적: 디지털 헬스를 이용한 재활치료가 치매환자의 인지 기능, 우울, activities of daily living (ADL), instrumental activities of daily living (IADL), 삶의 질에 미치는 영향을 확인한 연구들에 대해 고찰하고 그 효과를 알아보고자 하였다. 연구방법: 국외, 내 데이터베이스를 통해 2010년 1월부터 2022년 5월까지의 연구 중 총 15편의 무작위 대조군 실험연구를 선정하였다. Pedro scale을 통해 문헌의 질을 확인하였고, 디지털 헬스를 이용한 재활치료가 치매환자의 인지 기능, 우울, ADL, IADL, 삶의 질에 미치는 효과크기를 검정하고자 R 4.2.0을 사용하여 효과크기, 통계적 이질성, 출간오류 검정을 실시하였다. 결과: 선정된 15편의 논문의 평균 Pedro scale은 6.4점으로 비교적 높은 편에 속했으며, 15편의 연구는 전산화 인지재활 6편, 가상현실을 이용한 중재 5편, 원격재활 2편, 디지털 회상치료 1편, 로봇 1편으로 구성되었다. 메타분석 결과, 치매환자의 인지 기능(0.30, p = 0.01)과 우울(-0.71, p < 0.0001)에서 중간 효과크기로 나타났으며, 통계적으로 유의미하였다. 하지만 ADL (0.41, p = 0.26), IADL (0.20, p = 0.34), 삶의 질(0.31, p = 0.11)에서는 통계적으로 유의하지 않았다. 결론: 치매환자에게 디지털 헬스를 이용한 재활치료는 인지 기능을 향상시키고 우울을 감소시키는 것으로 나타났다. 이를 통해 인지 기능 감소와 우울 증상을 보이는 치매환자의 재활을 위해 디지털 헬스를 이용한 중재가 활용되기를 기대한다.

‘지역사회 계속거주(AIP: Aging in Place)’는 자율적이고 독립적인 노년의 삶을 원하는 노인들의 욕구 와 노인시설 운영비용 부담을 줄이고자 하는 정부의 필요성이 부합되면서 인구 고령화에 대처하는 새로운 패러다임으로서 주목받으며 활발히 논의되고 있다. AIP에 관한 국내외의 다양한 연구들은 AIP가 노년기의 삶의 질에 긍정적인 영향을 미치고 있음을 주장하는데, 이는 노인이 자립적으로 생활할 수 있는 사회환경이 제공되었을 때 가능하다. 본 연구는 사람이 살아가는데 가장 기본적인 필수 의료와 임종기 완화의료 및 돌봄 등의 실태를 점검하고 AIP 관련 정책의 현행 법령과 제도를 살펴봄으로써, 국가와 지방정부의 책무는 무엇이며 향후 그 책무를 충실히 이행하기 위한 실효적 방안들은 무엇인지에 관하여 제언한다.

Cardiovascular disease remains a leading global cause of mortality, demanding effective prevention and management. This systematic review explores the impact of lycopene, prevalent in various fruits, on cardiovascular health. Thirteen randomized and controlled trials were analyzed, involving 385 participants with cardiovascular risk factors. Notable findings included significant blood pressure reductions, particularly among hypertensive individuals, and favorable alterations in lipid profiles. Lycopene interventions also demonstrated potential in mitigating oxidative stress and inflammation markers. While these findings show promise, more rigorously designed studies are essential to determine optimal dosages and durations for precise cardiovascular benefits. In conclusion, lycopene shows potential in managing cardiovascular risk factors, and its role in blood pressure regulation, lipid profile improvement, and antioxidant and anti-inflammatory effects is encouraging. Nonetheless, further research is warranted to provide definitive guidance on integrating lycopene to enhance cardiovascular health.

교통안전특정해역은 해사안전법에 따라 설정되어 대형 해양사고를 막고 수 역 안전 및 항행 안전을 확보하는 목적을 지니고 있다. 하지만, 설정 범위에 있 어 국제법과 행정상의 원칙에 저촉되는 사안이 있다. 먼저, 바다의 헌법이라 불리는 해양법에 관한 국제연합협약(유엔해양법협약) 에 따른 접속수역에 교통안전특정해역이 설정되어 있으며 접속수역이 갖는 관 할권을 기준으로 본다면 교통안전특정해역과 관련된 모든 법령이 저촉되는 것은 아니지만, 대부분 법령이 저촉된다는 점을 알 수 있다. 특히 접속수역에서 보장되는 항행의 자유에 대한 침해가 주요한 문제라고 볼 수 있다. 이에 대한 해결방안으로 설정 수역 범위를 영해 내로 축소하거나 수역 안전 확보라는 공 익적 목적을 근거로 주변국의 인정을 받는 방법을 제시하였다. 또한, 행정기본법에 따른 비례의 원칙에 따라 울산구역과 포항구역을 살펴보 면 입법목적에 부합하지 않고 필요 이상으로 범위를 설정하여 공익 달성 없이 사익이 침해받는 구역이 있다. 이에 대한 해결방안으로 울산구역의 경우 거대 선 및 위험화물 운반선의 통항이 없는 저수심 구역의 제외를 제시하고, 포항구 역의 경우 실제 통항량이 존재하는 영일만 내로 범위를 한정하거나 혹은 유조 선통항금지구역 내로 범위를 한정하는 것을 제시하였다.

한국의 민주화운동인 4·19혁명, 5·18광주민주화운동 등은 법률에 따라 정신 계승과 선양이 이루어지고 있다. 1987년의 6월항쟁은 한국 민주화 운동의 대단원임에도 이에 대한 정신 계승과 선양을 위한 법·제도적인 근거가 없다. 본 연구는 6월항쟁에 대한 정신 계승과 선양에 사례를 검 토하여 그 한계를 극복하고자 한다. 6월항쟁에 대한 정신 계승과 선양은 교육과정, 민주화단체 등을 통해 이루어지고 있다. 첫째, 교육과정에서 6 월항쟁의 정신 계승은 6월항쟁 30주년 계기수업의 방식으로 도입되었다. 초등교육과정은 5학년의 도덕 과목과 6학년의 사회 과목에서 이루어졌 고, 중등교육과정은 역사 과목에서 읽기수업과 이야기수업으로 이루어졌 으며, 고등교육과정에서는 한국사 과목에서 강의방식과 토론방식으로 이 루어졌다. 둘째, 민주화운동단체들의 6월항쟁에 대한 정신 계승은 2020 년부터 6월항쟁 기념일을 포함해 1주일을 기념행사 기간으로 설정하여 전국적으로 기념식, 학술토론회, 음악회, 사진전 등 다양한 행사를 진행 하고 있다. 셋째, 6월항쟁의 선양은 관련 법률의 미제정으로 한계가 있 음에도 활용할 수 있는 선양 시설을 통해 부분적으로 이루어지고 있다. 결국 6월항쟁의 정신 계승과 선양을 위해서는 다른 민주화운동과의 형평 성에 근거하여 6월항쟁을 위한 법률 제정이 시급하다고 본다.

The primary objective of radiological environmental monitoring after a radiological emergency at a nuclear facility is acquisition of background data for the determination of protective actions for the population and the comprehensive assessment of the impact on the population residing in proximity to the nuclear facility. The responsible entities engaged in the conduct of the radiological environmental monitoring encompass government organization and nuclear licensees, operating in strict adherence to the national radiological disaster prevention framework. In accordance with the national radiological disaster prevention framework, radiation environmental monitoring is executed through the deployment of emergency response organization, and recurrent exercise drills aimed at augmenting responsible capabilities. In the context of radiation environmental monitoring, it is necessary to specify measurement parameters, monitoring location, and methodological protocols for each stage, considering potential exposure pathways. In terms of equipment, it is important to utilize mobile assets such as aerial or vehicle surveys for rapid and accurate radiation environment monitoring. Radiation disaster drills are regularly conducted, and the radiation environment monitoring field is also regularly trained to enhance response capabilities. The scale of these drills may vary, ranging from exclusive participation by nuclear licensees to joint exercises conducted by governmental agencies. This iterative process of periodic drills and equipment enhancements has led to a progressive augmentation of environmental monitoring capabilities, ensuring a well-coordinated orchestration of radiation monitoring within the framework of radiation protection. Notwithstanding these achievements, challenges in public communication regarding the decision to take protective actions and the dissemination of information to the public. Considering that the purpose of radiation environmental monitoring extends beyond safeguarding public health; it also serves to alleviate public anxiety. In the future, public communication between these stakeholders should also be included in disaster drill programs to ensure proper consultation between each stakeholder during drills and to build understanding and trust in radiation environmental monitoring. This is expected to improve the quality of radiation environmental monitoring response capabilities.

In the nuclear fuel cycle (NFC) facilities, the failure of Heating Ventilation and Air Conditioning (HVAC) system starts with minor component failures and can escalate to affecting the entire system, ultimately resulting in radiological consequences to workers. In the field of air-conditioning and refrigerating engineering, the fault detection and diagnosis (FDD) of HVAC systems have been studied since faults occurring in improper routine operations and poor preventive maintenance of HVAC systems result in excessive energy consumption. This paper aims to provide a systematic review of existing FDD methods for HVAC systems therefore explore its potential application in nuclear field. For this goal, typical faults and FDD methods are investigated. The commonly occurring faults of HVAC are identified through various literature including publications from International Energy Agency (IEA) and American Society of Heating, Refrigerating and Air-Conditioning Engineers (ASHRAE). However, most literature does not explicitly addresses anomalies related to pressure, even though in nuclear facilities, abnormal pressure condition need to be carefully managed, particularly for maintaining radiological contamination differently within each zone. To build simulation model for FDD, the whole-building energy system modeling is needed because HVAC systems are major contributors to the whole building’s energy and thermal comfort, keeping the desired environment for occupants and other purposes. The whole-building energy modeling can be grouped into three categories: physics-based modeling (i.e., white-box models), hybrid modeling (i.e., grey-box models), and data-driven modeling (i.e., black-box models). To create a white-box FDD model, specialized tools such as EnergyPlus for modeling can be used. The EnergyPlus is open source program developed by US-DOE, and features heat balance calculation, enabling the dynamic simulation in transient state by heat balance calculation. The physics based modeling has the advantage of explaining clear cause-and-effect relationships between inputs and outputs based on heat and mass transfer equations, while creating accurate models requires time and effort. Creating a black-box FDD model requires a sufficient quantity and diverse types of operational data for machine learning. Since operation data for HVAC systems in existing nuclear cycle facilities are not fully available, so efforts to establish a monitoring system enabling the collection, storage, and management of sensor data indicating the status of HVAC systems and buildings should be prioritized. Once operational data are available, well-known machine learning methods such as linear regression, support vector machines, random forests, artificial neural networks, and recurrent neural networks (RNNs) can be used to classify and diagnose failures. The challenge with black-box models is the lack of access to failure data from operating facilities. To address this, one can consider developing black-box models using reference failure data provided by IEA or ASHRAE. Given the unavailability of operation data from the operating NFC facilities, there is a need for a short to medium-term plan for the development of a physics-based FDD model. Additionally, the development of a monitoring system to gather useful operation data is essential, which could serve both as a means to validate the physics-based model and as a potential foundation for building data-driven model in the long term.

Wolsong Unit 1, a domestic heavy water reactor nuclear power plant, was permanently shut down in December 2019. Accordingly, Wolsong Unit 1 plans to prepare a Final Decommissioning Plan (FDP), submit it to the government by 2024, receive approval for decommissioning, and begin full-scale decommissioning. One of the important tasks in the decommissioning of Wolsong Unit 1 is to determine the decommissioning strategy. It is necessary to decide on a decommissioning strategy considering various factors and variables, secure the technical background, and justify it. The selection of a decommissioning strategy is best achieved through the use of formal decisionmaking assistance techniques, such as considerations related to influencing factors. It is very important to understand the basic decommissioning strategy alternatives and whether sufficient consideration has been given to situations where only a single unit is permanently shut down in a multi-unit site like Wolsong Unit 1, while the remaining units are in normal operation. As a process for selecting a decommissioning strategy, first, all considerations that could potentially affect decommissioning presented in the KINS Decommissioning Safety Review Guidelines were synthesized, influencing factors to be used in the decision-making process were determined, and the concept was defined. In order to select the most appropriate decommissioning strategy by considering various evaluation attributes of possible decommissioning alternatives (immediate dismantling and delayed dismantling), the Wolsong Unit 1 decommissioning strategy was evaluated by reflecting the AHP decision-making technique.

The nuclear power plant (NPP) decommissioning market is expected to expand not only domestically but also overseas. Proven technologies must be applied to decommission NPP. This is based on Article 41-2, Paragraph 2 of the domestic ‘Enforcement Decree Of The Nuclear Safety Act’. Proven technology refers to technology that has verified that it can be applied in the field through demonstration. In other words, in order to carry out NPP decommissioning, verification must be done. Demonstration refers to reducing technological uncertainty and directly verifying services implemented in the field. From a technology commercialization perspective, demonstration requires an approach based on technology readiness level (TRL) from a technology perspective and market readiness level (MRL) from a market perspective. The characteristics of demonstration also differ depending on the characteristics of each field. The demonstration in the field of nuclear energy is the demonstration of demand matching. This is to confirm the feasibility of the technology in the company’s required environment. In order to perform demonstration, a scenario must be derived by reflecting demonstration design considerations. After evaluating the derived scenario, an actual assessment is conducted using lab-based demonstration/virtual environment demonstration/real environment demonstration. What must be preceded by an actual assessment is confirming the consumer’s requirements. In this study, the necessary environment and requirements of consumer’s to perform NPP decommissioning were reviewed. The domestic decommissioning procedure requirements management system presents decommissioning procedures, potential worker accidents, and worker requirements. In the case of foreign countries, it was confirmed that complex wide need, cost benefit, risk reduction, waste generation, operation, reliability and maintenance (RAM) improvement and quantitative measures were evaluated for the technology to be demonstrated. Also the requirements for demonstrating decommissioning need to a detailed review of actual decommissioning cases. Therefore, a comparison must be made between the requirements based on actual NPP decommissioning cases and the requirements derived from this research process. Afterwards, the empirical research approach proposed by the Ministry of Trade, Industry and Energy was applied. The empirical research approach proposed by the Ministry of Trade, Industry and Energy is to secure a track record over a certain period of time and performance under conditions similar to the actual environment in the final research stage at the TRL level 6 to 8. Through this, it will be possible to confirm the suitability of overseas technology for domestic application.

The thermal treatment of radioactive waste attracts great attention. The thermal treatment offers lots of advantages, such as significant volume reduction, hazard reduction, increase of disposal safety, etc. There are various thermal technologies to waste. The developed technologies are calcination, incineration, melting, molten salt oxidation, plasma, pyrolysis, synroc, vitrification, etc. The off-gas treatment system is widely applied in the technologies to increase the safety and operation efficiency. The thermal treatment generates various by-product and pollutants during the process. The dust or fly ash are generated as a particulate from almost every radioactive waste. The treatment of PVC related components generates hydrogen chloride, which usually brings corrosion of facility. The treatment of rubber and spent resin generates sulfur oxide, SOx. The treatment of nitrile rubber generates nitrogen oxide, NOx. The incomplete combustion of radioactive waste usually generates carbon oxide, COx. The process temperature also affects the generation of off gas, such as NOx and/or COx. Various off gas treatment components are organized for the proper treatment of the previously mentioned materials. In this study systematical review on off gas treatment will be reported. Also, worldwide experiences and developed facility will be reported.

The primary purpose of high temperature process of radioactive waste is to satisfy the waste acceptance criteria and volume reduction. The WAC offers the guideline of waste form fabrication process. The WAC is defined as quantitative or qualitative criteria specified by the regulatory body, or specified by and operator and approved by the regulatory body, for radioactive waste to be accepted by the operator of a repository for disposal, or by the operator of a storage facility for storage. The main objective of WAC is to protect staff and general public and environment by the containment of radioactive material, limit external radiation level, and prevent criticality. The WAC also offers systematic management of radioactive waste by standardization of waste management operations, facilitation waste tracking, ensure safe and effective operation of operating facilities, etc. Since the high temperature process for radioactive waste is considered in many countries, lots of codes and standards are considered. In many WACs, compressive strength, thermal cycle stability, radiation exposure stability, free liquid, and leachability are evaluation to understand the effect of solidified form to the disposal facility. In this paper, systematical review on waste form will be discussed. In addition, brief result of characterization of waste form will be compared.

There are analytical methods used for measuring activity when light photons are emitted for scintillating-based analytical application. When this electron returns to the original stable state, it releases its energy in the form of light emission (visible light or ultraviolet light), and this phenomenon is called scintillation. Scintillator is a general term for substances that emit fluorescence when exposed to radiation such as gamma-rays. Radioactivity is all around us and is unavoidable because of the ubiquitous existence of background radiations emitted by different sources. The scintillator contributes to these sensing, and it is expected that the inspection accuracy and limit of detection will be improved and new inspection methods will be developed in the future. Moreover, scintillators are chemical or nanomaterial sensors that can be used to detect the presence of chemical species and elements or monitor physical parameters on the nanoscale. In this study, it includes finding use in scintillating-based analytical sensing applications. A chemical and nanomaterial based sensors are self-contained analytical tools that could provide information about the chemical compositions or elements of their environment, that is, a liquid or even gas condition. Herein, we present an insightful review of previously reported research in the development of high-performance gamma scintillators. The major performance-limiting factors of scintillation are summed up here. Moreover, the 2D material has been discussed in the context of these parameters. It will help in designing a prototype nanomaterial based scintillators for radiation detection of gamma-ray.