• 지역사회간호학회지
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• 제23권4호
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• pp.347-357
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• 2012

Purpose: The purpose of this study was to explore the experiences of family caregivers who care for the elderly under Long-term Care Insurance. Methods: Data were collected using focus group interviews and analyzed using a phenomenological approach. The four focus groups consisted of eight caregivers, two social workers and three nurses in B city, Korea. Results: Five themes were identified: 'Obtaining a care-helper certification for employment', 'Taking care of the elderly in their homes', 'Difficulties due to life changes', 'Difficulties due to reduced wages' and 'Dissatisfaction with the Long-term Care Insurance operating system'. Conclusion: The results of this study demonstrate that the long-term care system for family caregivers faces many systematic challenges in providing care for the elderly harmoniously in their home. To help them succeed in their tasks, Long-term Care Insurance system must offer respite and support programs to family caregivers.

• International Journal of Railway
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• 제6권1호
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• pp.26-31
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• 2013

Following the success of the KTX (Korea's first high-speed rail system) with a maximum operating speed of 300 km/h opened in 2004, experts in Korea started a research on the development of key technologies for high-speed rail (HSR) with a top speed of 500 km/h. This paper is a preliminary analysis of the research. It first reviews HSR experiences around the world, in terms of traffic and economic impacts of HSR, and presents a preliminary analysis of 500 km/h HSR in Korea. It is estimated that introduction of 500 km/h HSR with a 54% of travel time reduction will increase HSR passengers to about 9.8 million (about 78% of market share) between Seoul and Busan. It is a 23% of growth compared to the base scenario. Along with conventional rail passengers, air passengers are expected to be significantly impacted by the 500 km/h HSR. As a function of HSR travel time, the estimated market shares of both KTX and 500 km/h HSR compared to air are very comparable with previous international experiences. Based on the forecasted traffic, estimated total benefits are $758 million per year.

• 물과 미래
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• 제25권1호
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• pp.83-92
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• 1992

다목적 저수지의 운영을 위해서 여러 가지 대안의 운영율로부터 최상의 안을 선택할 때에는 시스템에 주어진 주요 목적에 부가하여 세부적인 평가 기준들도 고려하여야 한다. 특히 평가 단위가 서로 다른 여러개의 평가기준을 고려할 때에는 경험이나 발견법 만으로는 최상의 안을 선택하기가 어렵게 된다. 다기준 의사 분석기법을 이요하면 여러대안들을 각 평가 기준에 다라 체계적으로 비교하여 대안들의 우선 순위를 결정함으로써 최상의 운영율을 선택할 수 있다. 본 연구에서는 다목적 저수지 시스템의 운영율 평가를 위한 평가 기준을 규명하여 제시하였으며, 다기준 의사분석 기법을 이용하여 충주 다목적 저수지 시스템에 대한 4개의 운영율을 9개의 평가 기준에 따라 평가하였다. 적용 결과 대규모 다목적 저수지 시스템의 운여오가 같이 많은 평가기준을 고려하여 여러 가지 대안의 운영율을 평가할 때에는 이러한 기법이 매우 효율적임을 알 수 있다.

• Nuclear Engineering and Technology
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• 제40권4호
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• pp.255-268
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• 2008

The greater demand for electricity and the available capacity within safety margins in some operating NPPs are prompting nuclear utilities to request license modification to enable operation at a higher power level, beyond their original license provisions. Such plant modifications require an in-depth safety analysis to evaluate the possible safety impact. The analysis must consider the thermo hydraulic, radiological and structural aspects, and the plant behavior, while taking into account the capability of the structures, systems and components, and the reactor protection and safeguard systems set points. The purpose of this paper is to introduce international experiences and approaches for implementation of power uprates related to the reactor thermal power of nuclear power plants. The paper is intended to give the reader a general overview of the major processes, work products, issues, challenges, events, and experiences in the power uprates program. The process of increasing the licensed power level of a nuclear power plants is called a power uprate. One way of increasing the thermal output from a reactor is to increase the amount of fissile material in use. It is also possible to increase the core power by increasing the performance of the high power bundles. Safety margins can be maintained by either using fuels with a higher performance, or through the use of improved methods of analysis to demonstrate that the required margins are retained even at the higher power levels. The paper will review all types of power uprates, from small to large, and across various reactor types, including light and heavy water, pressurized, and boiling water reactors. Generally, however, the content of the report focuses on power uprates of the stretch and extended type. The International Atomic Energy Agency (IAEA) is developing a technical guideline on power uprates and side effects of power uprates in nuclear power plants.

• 한국콘텐츠학회논문지
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• 제20권12호
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• pp.166-179
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• 2020

이 연구의 목적은 서울대 내부 구성원의 인식과 경험을 중심으로 법인화 이후 서울대가 무엇이 변화되었는지를 탐색적으로 분석하는 것이다. 이를 위해 서울대 내부 구성원인, 교수, 직원, 학생을 대상으로 반구조화된 면담을 실시하였다. 면담결과는 서울대 법인화에 대한 전반적 평가, 법인화에 따른 긍정적 및 부정적 변화, 교육, 연구, 사회공헌, 그리고 운영체제 측면에서 변화로 구분하여 제시하였다. 전반적으로 볼 때, 법인화 이후의 변화에 대해 서울대 내부 구성원들은 변화를 체감하기 어렵거나 변화가 별로 없다는 공통적인 인식을 보였다. 긍정적 변화로는 대학 재정의 확대와 운영의 자율성 확대, 환경변화에 대한 대응력 향상을, 부정적 변화로는 서울대의 법적 지위 모호, 대학 외부로부터의 직접적이고 공격적인 영향력의 과도한 증가를 언급하였다. 마지막 부분에서는 주요 결과를 정리하면서, 그 의미와 시사점에 관해 논의하였다.

• 한국산학기술학회논문지
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• 제11권10호
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• pp.3885-3892
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• 2010

원자력발전소의 발전소보호계통과 같은 안전필수 시스템은 예상 가능한 사고로부터 인간과 자연을 보호하기 위한 중요 기능을 수행하는 시스템으로써, 어떠한 조건 하에서도 고유의 안전기능을 안정적으로 수행할 수 있도록 설계되어야 한다. 원자력발전소의 안전필수 기능을 수행하는 계측제어시스템에 적용되는 최신의 컴퓨터에는 다양한 하부기기를 감시 및 제어하고, 응용 프로그램을 실행시키기 위한 실시간 운영체제가 탑재되어 있으며, 이러한 실시간 운영체제는 가장 엄격한 소프트웨어 품질이 요구된다. 또한, 예상 가능한 조건에서도 안전필수 시스템의 기능이 적절히 수행될 수 있도록 설계, 분석 및 평가되어야 한다. 그러나 지금까지 국내 원자력발전소 안전필수 시스템에는, 원자력 기준과 품질등급에 따라 개발된 제품이 아닌 상용제품의 실시간 운영체제를 정성적 측면에서 승인(Commercial Grade Item Dedication)하는 방식으로 적용되어 왔다. 이로 인해 실시간 운영체제가 안전필수 기능을 수행하는 데 적합한지를 평가하는 상세 방법론과 경험이 매우 부족한 것으로 파악되고 있다. 특히, 안전필수 시스템에 적용함을 목적으로 신규 개발되는 실시간 운영체제의 경우, 안전성을 평가하기 위한 적절한 방법을 도출하기에 어려움이 있는 것으로 파악되고 있다. 본 논문에서는 원전의 안전필수 기능을 수행하는 실시간 운영체제의 설계요구사항을 기반으로, 안전필수 실시간 운영체제에 대한 안전성 분석 및 평가 사례를 제시하고자 한다. 본 논문에서 제시한 상세 안전성 평가의 방법과 사례는 향후 타 산업분야에서의 안전필수 실시간 운영체제 개발 및 안전성 평가에 활용될 수 있을 것으로 기대된다.

• KSII Transactions on Internet and Information Systems (TIIS)
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• 제7권5호
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• pp.998-1013
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• 2013

Wireless wearable sensor networks have emerged as a promising technique for human motion tracking due to the flexibility and scalability. In such system several wireless sensor nodes being attached to human limb construct a wearable sensor network, where each sensor node including MEMS sensors (such as 3-axis accelerometer, 3-axis magnetometer and 3-axis gyroscope) monitors the limb orientation and transmits these information to the base station for reconstruction via low-power wireless communication technique. Due to the energy constraint, the high fidelity requirement for real time rendering of human motion and tiny operating system embedded in each sensor node adds more challenges for the system implementation. In this paper, we discuss such challenges and experiences in detail during the implementation of such system with wireless wearable sensor network which includes COTS wireless sensor nodes (Imote 2) and uses TinyOS 1.x in each sensor node. Since our system uses the COTS sensor nodes and popular tiny operating system, it might be helpful for further exploration in such field.

• 한국압력기기공학회 논문집
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• 제9권1호
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• pp.20-24
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• 2013

Reactor Vessel Internals(RVIs), which are installed within the reactor pressure vessel and support the fuel assembly, take responsibility for safety of reactor core. In operating Nuclear Power Plants(NPPs), the RVIs have been exposed to severe conditions such as neutron irradiation, high temperature, high pressure, and high velocity of coolant flow and have degraded by materials aging with long-term operation. Therefore, the effective aging management plan and the appropriate regulatory requirements are necessary to maintain the integrity of RVIs. The purpose of this paper is to provide a review guide for Periodic Safety Review(PSR) of RVIs in presurized water reactor. The review guide is developed based on the revised review guides and reports established from IAEA and USNRC, and the analysis results of design characteristics, aging mechanisms, and operating experiences of RVIs in domestic and international NPPs. Consequently, the developed review guide for PSR of RVIs is expected to contribute an overall strategy and standard for the PSR of RVIs.

• 한국유체기계학회 논문집
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• 제13권5호
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• pp.5-10
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• 2010

5MW, open pool type research reactor, is commonly used to education and experimental purpose. It is necessary to prepare a standardization of system designs for considering a demand. HANARO has prepared the standardization of 5MW research reactor system designs based on the design, installation, commissioning and operating experiences of HANARO. For maintaining an open pool type reactor safety, a primary cooling system (after below, PCS) should remove the heat generated by the reactor under a reactor normal operation condition and a reactor shutdown condition. For removing the heat generated by the reactor, the PCS should maintain a required coolant flow rate. For a verification of the required flow rate, a flow network analysis of the PCS was carried under a normal operating condition. Based on the flow network analysis result, this paper describes the PCS flow characteristics of a 5MW open pool type research reactor. Through the result, it was confirmed that the PCS met design requirements including design flow rate without cavitation.

• Nuclear Engineering and Technology
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• 제41권4호
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• pp.545-548
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• 2009

Korean utility has utilized a Periodic Safety Review (PSR) that assesses the cumulative effects of plant aging, modifications, operating experience, technical developments, and site characteristics since 2000. In particular, the assessment and management of plant aging is one of the major areas in PSR. It includes identification of critical Systems, Structures, and Components (SSCs) for aging, assessment of aging effects, and implementation of aging management programs. Since the PSR system was introduced based on the atomic energy acts and related laws, PSRs of eight sets for 12 Nuclear Power Plants (NPPs) that have been operating more than 10 years have been completed. PSRs of two sets for 4 NPPs are currently being carried out. The utility has confirmed that domestic NPPs have been operated safely through these PSRs and have implemented the follow-up corrective activities to increase the nuclear safety. In this paper, the status of PSR implementation is discussed and improvement programs to conduct PSR follow-up corrective activities efficiently for NPPs are suggested based on experiences with aging assessments.