• Title/Summary/Keyword: safety net

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The Structural Model Suicidal Ideation in Elderly Living Alone (독거노인의 자살생각에 대한 구조모형 분석)

  • Kim, Jeong-Suk
    • Journal of Convergence for Information Technology
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    • v.8 no.2
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    • pp.29-36
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    • 2018
  • This study was conducted to analyze the model of suicide ideation in the elderly living alone. This study is a descriptive research study of 300 elderly living alone in C-region. It is a frequency analysis, correlation analysis, simple rare analysis. AMOS statistics were performed. Data collection was from October 1, 2016 to December 31, 2016. The results of this study are as follows. Family support has a direct effect on suicidal ideation(need for suicide ${\beta}=-.362$, p=.000, negative attitudes toward life ${\beta}=-.259$, p=.001). The results of this study suggest that strengthening the family support and social activities of the elderly living alone reduces the suicidal ideation and builds the social safety net, which leads to the emotional stability and the related policy establishment.

Competencies of Dental Hygienists for Oral Care Service for People with Disability

  • Lee, Jae-Young;Kim, Young-Jae;Jin, Bo-Hyoung
    • Journal of dental hygiene science
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    • v.20 no.1
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    • pp.16-24
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    • 2020
  • Background: Dental treatment has shifted to the center of the community, and the public policy of the country has expanded to support the vulnerable classes such as the disabled. The dental profession needs education regarding oral health services for persons with disabilities, and it is necessary to derive the competencies for this. Therefore, we conducted this study to derive the normative ability to understand the role of a dental hygienist in the oral health service for persons with disabilities and improvement plans for education. Methods: We conducted a qualitative analysis for deriving competencies by analyzing the data collected through in-depth interviews with experts in order to obtain abilities through practical experience. Based on the competency criterion, relevant competency in the interview response was derived using the priori method, and it was confirmed whether the derived ability matched the ability determined by the respondent. Results: The professional conduct competencies of dental hygienists, devised by the Korean Association of Dental Hygiene, consists of professional behavior, ethical decision-making, self-assessment skills, lifelong learning, and accumulated evidence. Also, core competencies of the American Dental Education Association competencies for dental hygienist classification such as ethics, responsibility for professional actions, and critical thinking skills were used as the criterion. The dental hygienist's abilities needed for oral health care for people with disabilities, especially in the detailed abilities to fulfill these social needs, were clarified. Conclusion: To activate oral health care for people with disabilities, it is necessary for dental hygienists to fulfill their appropriate roles, and for this purpose, competency-based curriculum restructuring is indispensable. A social safety net for improving the oral health of people with disabilities can be secured by improving the required skills-based education system of dental hygienists and strengthening the related infrastructure.

Multidimensional Factors Influencing Health of Low-Income Women: The Moderating Effect of Social Support Resource (저소득층 여성의 건강에 영향을 미치는 다차원적 요인 : 사회적 지지 자원의 조절효과)

  • Kim, Miyoung
    • Journal of Digital Convergence
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    • v.16 no.7
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    • pp.479-491
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    • 2018
  • This study aims to figure out factors influencing health and moderating effect of social support resource between those factors and health of low income women in diverse spheres. The data of low income women were 239 cases and were utilized SPSS ver. 21 program. The main results of this study are as follows: firstly, health of low income women is identified medium level. Secondly, education level, self-efficacy and social support resource are related to the self-rated health of low income women. Especially, social support resource functions as moderators on between education and self-rated level of the health of low income women. Consequently, the findings suggest the need to expand the social intervention range to promote health of low income women from cost benefit to psychological support such as capacity building for self-management and establishment of safety-net to extend social support. And subsequently, the time attribute of the factors related to low-income women's health and the diverse characteristics of the subjects should be considered.

An Algorithm of Identifying Roaming Pedestrians' Trajectories using LiDAR Sensor (LiDAR 센서를 활용한 배회 동선 검출 알고리즘 개발)

  • Jeong, Eunbi;You, So-Young
    • The Journal of The Korea Institute of Intelligent Transport Systems
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    • v.16 no.6
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    • pp.1-15
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    • 2017
  • Recently terrorism targets unspecified masses and causes massive destruction, which is so-called Super Terrorism. Many countries have tried hard to protect their citizens with various preparation and safety net. With inexpensive and advanced technologies of sensors, the surveillance systems have been paid attention, but few studies associated with the classification of the pedestrians' trajectories and the difference among themselves have attempted. Therefore, we collected individual trajectories at Samseoung Station using an analytical solution (system) of pedestrian trajectory by LiDAR sensor. Based on the collected trajectory data, a comprehensive framework of classifying the types of pedestrians' trajectories has been developed with data normalization and "trajectory association rule-based algorithm." As a result, trajectories with low similarity within the very same cluster is possibly detected.

VERIFICATION OF ELECTROMAGNETIC EFFECTS FROM WIRELESS DEVICES IN OPERATING NUCLEAR POWER PLANTS

  • YE, SONG-HAE;KIM, YOUNG-SIK;LYOU, HO-SUN;KIM, MIN-SUK;LYOU, JOON
    • Nuclear Engineering and Technology
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    • v.47 no.6
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    • pp.729-737
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    • 2015
  • Wireless communication technologies, especially smartphones, have become increasingly common. Wireless technology is widely used in general industry and this trend is also expected to grow with the development of wireless technology. However, wireless technology is not currently applied in any domestic operating nuclear power plants (NPPs) because of the highest priority of the safety policy. Wireless technology is required in operating NPPs, however, in order to improve the emergency responses and work efficiency of the operators and maintenance personnel during its operation. The wired telephone network in domestic NPPs can be simply connected to a wireless local area network to use wireless devices. This design change can improve the ability of the operators and personnel to respond to an emergency situation by using important equipment for a safe shutdown. IEEE 802.11 smartphones (Wi-Fi standard), Internet Protocol (IP) phones, personal digital assistant (PDA) for field work, notebooks used with web cameras, and remote site monitoring tablet PCs for on-site testing may be considered as wireless devices that can be used in domestic operating NPPs. Despite its advantages, wireless technology has only been used during the overhaul period in Korean NPPs due to the electromagnetic influence of sensitive equipment and cyber security problems. This paper presents the electromagnetic verification results from major sensitive equipment after using wireless devices in domestic operating NPPs. It also provides a solution for electromagnetic interference/radio frequency interference (EMI/RFI) from portable and fixed wireless devices with a Wi-Fi communication environment within domestic NPPs.

LEAK-BEFORE-BREAK ANALYSIS OF THERMALLY AGED NUCLEAR PIPE UNDER DIFFERENT BENDING MOMENTS

  • LV, XUMING;LI, SHILEI;ZHANG, HAILONG;WANG, YANLI;WANG, ZHAOXI;XUE, FEI;WANG, XITAO
    • Nuclear Engineering and Technology
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    • v.47 no.6
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    • pp.712-718
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    • 2015
  • Cast duplex stainless steels are susceptible to thermal aging during long-term service at temperatures ranging from $280^{\circ}C$ to $450^{\circ}C$. To analyze the effect of thermal aging on leak-before-break (LBB) behavior, three-dimensional finite element analysis models were built for circumferentially cracked pipes. Based on the elasticeplastic fracture mechanics theory, the detectable leakage crack length calculation and J-integral stability assessment diagram approach were carried out under different bending moments. The LBB curves and LBB assessment diagrams for unaged and thermally aged pipes were constructed. The results show that the detectable leakage crack length for thermally aged pipes increases with increasing bending moments, whereas the critical crack length decreases. The ligament instability line and critical crack length line for thermally aged pipes move downward and to the left, respectively, and unsafe LBB assessment results will be produced if thermal aging is not considered. If the applied bending moment is increased, the degree of safety decreases in the LBB assessment.

Dynamic Analysis of AP1000 Shield Building Considering Fluid and Structure Interaction Effects

  • Xu, Qiang;Chen, Jianyun;Zhang, Chaobi;Li, Jing;Zhao, Chunfeng
    • Nuclear Engineering and Technology
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    • v.48 no.1
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    • pp.246-258
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    • 2016
  • The shield building of AP1000 was designed to protect the steel containment vessel of the nuclear reactor. Therefore, the safety and integrity must be ensured during the plant life in any conditions such as an earthquake. The aim of this paper is to study the effect of water in the water tank on the response of the AP1000 shield building when subjected to three-dimensional seismic ground acceleration. The smoothed particle hydrodynamics method (SPH) and finite element method (FEM) coupling method is used to numerically simulate the fluid and structure interaction (FSI) between water in the water tank and the AP1000 shield building. Then the grid convergence of FEM and SPH for the AP1000 shield building is analyzed. Next the modal analysis of the AP1000 shield building with various water levels (WLs) in the water tank is taken. Meanwhile, the pressure due to sloshing and oscillation of the water in the gravity drain water tank is studied. The influences of the height of water in the water tank on the time history of acceleration of the AP1000 shield building are discussed, as well as the distributions of amplification, acceleration, displacement, and stresses of the AP1000 shield building. Research on the relationship between the WLs in the water tank and the response spectrums of the structure are also taken. The results show that the high WL in the water tank can limit the vibration of the AP1000 shield building and can more efficiently dissipate the kinetic energy of the AP1000 shield building by fluid-structure interaction.

A Concise Design for the Irradiation of U-10Zr Metallic Fuel at a Very Low Burnup

  • Guo, Haibing;Zhou, Wei;Sun, Yong;Qian, Dazhi;Ma, Jimin;Leng, Jun;Huo, Heyong;Wang, Shaohua
    • Nuclear Engineering and Technology
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    • v.49 no.4
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    • pp.734-743
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    • 2017
  • In order to investigate the swelling behavior and fuel-cladding interaction mechanism of U-10Zr alloy metallic fuel at very low burnup, an irradiation experiment was concisely designed and conducted on the China Mianyang Research Reactor. Two types of irradiation samples were designed for studying free swelling without restraint and the fuel-cladding interaction mechanism. A new bonding material, namely, pure aluminum powder, was used to fill the gap between the fuel slug and sample shell for reducing thermal resistance and allowing the expansion of the fuel slug. In this paper, the concise irradiation rig design is introduced, and the neutronic and thermal-hydraulic analyses, which were carried out mainly using MCNP (Monte Carlo N-Particle) and FLUENT codes, are presented. Out-of-pile tests were conducted prior to irradiation to verify the manufacturing quality and hydraulic performance of the rig. Nondestructive postirradiation examinations using cold neutron radiography technology were conducted to check fuel cladding integrity and swelling behavior. The results of the preliminary examinations confirmed the safety and effectiveness of the design.

Drop Performance Test of Conceptually Designed Control Rod Assembly for Prototype Generation IV Sodium-Cooled Fast Reactor

  • Lee, Young-Kyu;Lee, Jae-Han;Kim, Hoe-Woong;Kim, Sung-Kyun;Kim, Jong-Bum
    • Nuclear Engineering and Technology
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    • v.49 no.4
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    • pp.855-864
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    • 2017
  • The control rod assembly controls reactor power by adjusting its position during normal operation and shuts down chain reactions by its free drop under scram conditions. Therefore, the drop performance of the control rod assembly is important for the safety of a nuclear reactor. In this study, the drop performance of the conceptually designed control rod assembly for the prototype generation IV sodium-cooled fast reactor that is being developed at the Korea Atomic Energy Research Institute as a next-generation nuclear reactor was experimentally investigated. For the performance test, the test facility and test procedure were established first, and several free drop performance tests of the control rod assembly under different flow rate conditions were then carried out. Moreover, performance tests under several types and magnitudes of seismic loading conditions were also conducted to investigate the effects of seismic loading on the drop performance of the control rod assembly. The drop time of the conceptually designed control rod assembly for 0% of the tentatively designed flow rate was measured to be 1.527 seconds, and this agrees well with the analytically calculated drop time. It was also observed that the effect of seismic loading on the drop time was not significant.

Valve core shapes analysis on flux through control valves in nuclear power plants

  • Qian, Jin-yuan;Hou, Cong-wei;Mu, Juan;Gao, Zhi-xin;Jin, Zhi-jiang
    • Nuclear Engineering and Technology
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    • v.52 no.10
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    • pp.2173-2182
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    • 2020
  • Control valves are widely used to regulate fluid flux in nuclear power plants, and there are more than 1500 control valves in the primary circuit of one nuclear power plant. With their help, the flux can be regulated to a specific level of water or steam to guarantee the energy efficiency and safety of the nuclear power plant. The flux characteristics of the control valve mainly depend on the valve core shape. In order to analyze the effects of valve core shapes on flux characteristics of control valves, this paper focuses on the valve core shapes. To begin with, numerical models of different valve core shapes are established, and results are compared with the ideal flux characteristics curve for the purpose of validation. Meanwhile, the flow fields corresponding to different valve core shapes are investigated. Moreover, relationships between the valve core opening and the outlet flux under different valve core shapes are carried out. The flux characteristics curve and equation are proposed to predict the outlet flux under different valve core openings. This work can benefit the further research of the flux control and the optimization of the valve core for control valves in nuclear power plants.