• The Journal of the Korea Contents Association
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• v.16 no.9
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• pp.136-148
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• 2016

This study was carried out to analyze the consumption expenditure condition of elderly persons with and without physical disabilities by social economic status and sociodemographic characteristics and to compare the results of those two groups for making an offer the basic materials to provide political support for elderly persons with physical disabilities. The statistical analysis of collected data was enforced through T-test, ANOVA and Crosstabs with SPSS 19.0 program. The results of this study are summarized as follows. First, the group with disabilities has presumed to be in relative poverty given that disposable income, academic career and total living expenses showed lower than the other group. Second, the component ratios of domestic foods and housing expenses of disabled group showed higher but those of specific spending items of expenditure such as social activities, reserving fund of social security for economic safety net, clothing and eating out expenses showed lower than the other group.

• The Journal of the Korea Contents Association
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• v.18 no.10
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• pp.145-157
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• 2018

In this study, we analyzed the effect of the income level of cancer, stroke, and myocardial infarction on mortality by using National Health Insurance Service(NHIS) Cohort 2.0 DB. Patients who newly developed the disease in 2007 were observed till 2015. The analysis used the Cox probability proportional risk model and the competing risk model. The income level used information at the time of the onset of the disease in 2007, categorized into low / mid / high. The results showed that there were differences in the risks of death and secondary disease in patients with cancer, stroke, or myocardial infarction according to the income level. In addition to the need for a social safety net to lower the incidence of early deaths in low-income families, it seems necessary to continue to strengthen universal protection for serious diseases similar to the current policy.

• Nuclear Engineering and Technology
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• v.46 no.3
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• pp.313-342
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• 2014

A Nuclear Energy Agency (NEA), Organization for Economic Co-operation and Development (OECD) benchmark for Uncertainty Analysis in Modeling (UAM) is defined in order to facilitate the development and validation of available uncertainty analysis and sensitivity analysis methods for best-estimate Light water Reactor (LWR) design and safety calculations. The benchmark has been named the OECD/NEA UAM-LWR benchmark, and has been divided into three phases each of which focuses on a different portion of the uncertainty propagation in LWR multi-physics and multi-scale analysis. Several different reactor cases are modeled at various phases of a reactor calculation. This paper discusses Phase I, known as the "Neutronics Phase", which is devoted mostly to the propagation of nuclear data (cross-section) uncertainty throughout steady-state stand-alone neutronics core calculations. Three reactor systems (for which design, operation and measured data are available) are rigorously studied in this benchmark: Peach Bottom Unit 2 BWR, Three Mile Island Unit 1 PWR, and VVER-1000 Kozloduy-6/Kalinin-3. Additional measured data is analyzed such as the KRITZ LEU criticality experiments and the SNEAK-7A and 7B experiments of the Karlsruhe Fast Critical Facility. Analyzed results include the top five neutron-nuclide reactions, which contribute the most to the prediction uncertainty in keff, as well as the uncertainty in key parameters of neutronics analysis such as microscopic and macroscopic cross-sections, six-group decay constants, assembly discontinuity factors, and axial and radial core power distributions. Conclusions are drawn regarding where further studies should be done to reduce uncertainties in key nuclide reaction uncertainties (i.e.: $^{238}U$ radiative capture and inelastic scattering (n, n') as well as the average number of neutrons released per fission event of $^{239}Pu$).

• Nuclear Engineering and Technology
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• v.52 no.3
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• pp.597-609
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• 2020

Accident Tolerant Fuels have been widely studied since the Fukushima-Daiichi accident in 2011 as one of the options on how to further enhance the safety of nuclear power plants. Deposition of protective coatings on nuclear fuel claddings has been considered as a near-term concept that will reduce the high-temperature oxidation rate and enhance accidental tolerance of the cladding while providing additional benefits during normal operation and transients. This study focuses on experimental testing of Zr-based alloys coated with Cr-based coatings using Physical Vapour Deposition. The results of long-term corrosion tests, as well as tests simulating postulated accidents, are presented. Zr-1%Nb alloy used as nuclear fuel cladding serves as a substrate and Cr, CrN, Cr_xN_y layers are deposited by unbalanced magnetron sputtering and reactive magnetron sputtering. The deposition procedures are optimized in order to improve coating properties. Coated as well as reference uncoated samples were experimentally tested. The presented results include standard long-term corrosion tests at 360℃ in WWER water chemistry, burst (creep) tests and mainly single and double-sided high-temperature steam oxidation tests between 1000 and 1400℃ related to postulated Loss-of-coolant accident and Design extension conditions. Coated and reference samples were characterized pre- and post-testing using mechanical testing (microhardness, ring compression test), Thermal Evolved Gas Analysis analysis (hydrogen, oxygen concentration), optical microscopy, scanning electron microscopy (EDS, WDS, EBSD) and X-ray diffraction.

• Nuclear Engineering and Technology
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• v.52 no.7
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• pp.1571-1578
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• 2020

As a critical material in very/high-temperature gas-cooled reactors, graphite material directly affects the safety of the reactor core structures. Owing to the complex structures of graphite material in reactors, the material typically undergoes complex stress states. It is, therefore, necessary to study its mechanical properties, failure modes, and strength criteria under complex stress states so as to provide guidance for the core structure design. In this study, compressive failure tests were performed for graphite material under the condition of different confining pressures, and the effects of confining pressure on the triaxial compressive strength and Young's modulus of graphite material were studied. More specifically, graphite material based on the fracture surfaces and fracture angles, the graphite specimens were found to exhibit four types of failure modes, i.e., tension failure, shear-tension failure, tension-shear failure and shear failure, with increasing confining pressure. In addition, the Mohr strength envelope of the graphite material was obtained, and different strength criteria were compared. It showed that the parabolic Mohr-Coulomb criterion is more suitable for the strength evaluation for the graphite material.

• Nuclear Engineering and Technology
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• v.52 no.8
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• pp.1732-1741
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• 2020

The structural integrity of welded joints in the reactor pressure vessel (RPV) is directly related to the safety of nuclear power plants. The RPV is made from SA508-III steel in a pressurized water reactor. In this study, we investigated the effects of temperature on the tensile and fracture toughness properties of Chinese SA508-III welded joint in different sampling areas in order to provide reference data for structural integrity assessments of RPVs. The specimens used in tensile and fracture toughness tests were fabricated from the base metal (BM), weld metal (WM), and the heat-affected zone (HAZ) in the welded joint. The representative testing temperatures included the ambient temperature (20 ℃), upper shelf temperature (100 ℃), and service temperature (320 ℃). The results showed that temperature greatly affected the fracture toughness (JIC) values for the SA508-III welded joint. The JIC values for BM and HAZ both decreased remarkably from 20 ℃ to 320 ℃. The fracture morphologies showed that the BM and HAZ in the welded joint exhibited fully ductile fracture at 20 ℃, whereas partial cleavage fracture was mixed in ductile fracture mode at 100 ℃ and 320 ℃. The WM exhibited the ductile and cleavage fracture mixed mode at various temperatures, and the JIC values showed slight changes.

• Nuclear Engineering and Technology
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• v.52 no.8
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• pp.1784-1791
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• 2020

The 14 MeV neutron generator facility is being developed by the Institute for Plasma Research India to conduct the lab scale experiments related to Indian breeding blanket system for ITER and DEMO. It will also be utilized for material testing, shielding experiments and development of fusion diagnostics. Occupational radiation exposure control is necessary for the all kind of nuclear facilities to get the operational licensing from governing authorities and nuclear regulatory bodies. In the same way, the radiation exposure for the 14 MeV neutron generator facility at the occupational worker area and accessible zones for general workers should be under the permissible limit of AERB India. The generator is designed for the yield of 10¹² n/s. The shielding assessment has been made to estimate the radiation dose during the operational time of the neutron generator. The facility has many utilities and constraints like ventilation ducts, accessible doors, accessibility of neutron generator components and to conduct the experiments which make the shielding assessment challenging to provide proper safety for occupational workers and the general public. The neutron and gamma dose rates have been estimated using the MCNP radiation transport code and ENDF -VII nuclear data libraries. The ICRP-74 fluence to dose conversion coefficients has been used for the assessment. The annual radiation exposure has been assessed by considering 500 h per year operational time. The provision of local shield near to neutron generator has been also evaluated to reduce the annual radiation doses. The comprehensive results of radiation shielding capability of neutron generator building and local shield design have been presented in the paper along with detailed maps of radiation field.

• Korea Journal of Hospital Management
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• v.18 no.3
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• pp.106-125
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• 2013

Medical litigation, as a method of resolving medical disputes, has been a huge burden on both the patient and medical institution as it is both costly and time-consuming. The Korea Medical Dispute Mediation and Arbitration Agency has created a dispute mediation process as a method of alternative dispute resolution(ADR). Being in its early stage of implementation, there are still areas requiring improvement as some functions overlap with the Korea Consumer Agency's damage redress and mediation process. This study examines the problems of existing practices in medical litigation while reviewing the mediation process of the two agencies from legal/administrative aspects, and provides an in-depth analysis of the situation through case studies and interviews. While the Korea Medical Dispute Mediation and Arbitration Agency offers many advantages in resolving medical disputes, there must be a distinct division of roles and mutual cooperation with the Korea Consumer Agency. Considering the increasing amount of compensation in medical disputes, medical professionals are being requested to carry medical malpractice insurance. However, this has yet to become a general trend in the medical field despite the growing social demand. As such, the coverage of medical malpractice insurance should be expanded to prevent medical accidents from escalating into medical disputes, thus acting as a social safety net. This study seeks to examine the methods of medical dispute resolution and to allow institutional provisions to reduce the social costs arising from such disputes.

• Proceedings of the Korean Institute of Navigation and Port Research Conference
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• v.29 no.1
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• pp.125-129
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• 2005

This study aims to provide divers with improved safe diving practices by analyzing reports on scuba diving casualties that recently(from 1997-2003)occurred in Korea, Japan and USA. The result of this study can contribute toward preventing the diving accident. All the data were collected through the diving accident reports of various sourse, which include KUA(Korea Underwater Association) technical committee, the accident statistical data of National Maritime Police Agency, articles of domestic and foreign scuba diving magazine, accident reports of various newspaper, annual report on decompression illness and diving fatalities by DAN(Diver Alert Network), various type of data on diving accident from local as well as national seminars, and medical treatment data of diving accident.

• Journal of the Korean Society of Manufacturing Process Engineers
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• v.15 no.6
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• pp.83-88
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• 2016

Over the last five years, 568 people have died while hiking according to 2015 statistics from the public safety ministry. Among those deaths, approximately 33% were due to loss of footing or falling. In this respect, the highly advanced functions of hiking boots should be considered to prevent these unfortunate accidents. For example, by utilizing the Internet of Things (IoT) and Information and Communications Technology (ICT), hiking boots equipped with a Global Positioning System (GPS) or vital signs monitoring systems should be considered. In addition, many challenges remain for the production of 3D printed hiking boots, because the functions of hiking boots are variable, which is important when handling changing terrains and situations. The design of customized hiking boots was introduced in this paper, and 3D printing applications for midsoles using a Porous Polymer Printing (PPP) method was also suggested to verify the possibility of manufacturing hiking boots.