• Journal of Korean Public Health Nursing
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• v.29 no.3
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• pp.403-411
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• 2015

Due to lack of an information system regarding the status of using home-visit nursing (HVN), it has barriers of providing improvement of the HVN for management of elderly health care in Korea. The twofold aims of the current review are to expose the existing agendas for HVN and to suggest the political implications for HVN of Korea based on the transition process and revised HVN system of Japan. This review suggests that an information evaluation system has to precede for HVN services in detail. And, the service provided per manpower should be assessed by separating the code of manpower (registered nurse, nurse aide, dental hygienist) as well as securing detailed and precise information on the HVN services. The other suggestion, development of a community-based home health care nursing model in order to provide necessary services for long-term health insurance beneficiaries. In addition, a master plan for health care for elderly should be established at the national level in order to establish an effective home health nursing delivery system.

• Nuclear Engineering and Technology
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• v.51 no.3
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• pp.837-842
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• 2019

A large amount of radioactive material was released from the Fukushima Daiichi Nuclear Power Plant (FDNPP) in 2011 and dispersed into the environment. Though seven years have passed since the Fukushima Daiichi Nuclear Power Plant accident, some parts of Japan are still under the influence of radionuclide contamination, especially Fukushima Prefecture and prefectures neighboring Fukushima Prefecture. The long-term effective doses and the contributions of each exposure pathway (5 exposure pathways) and radionuclide ($^{131}I$, $^{134}Cs$, and $^{137}Cs$) were evaluated for people living in the regions of Fukushima and neighboring prefectures in Japan using a developed dose assessment code system with Japanese specific input data. The results estimated in this study were compared with data from previously published reports. Groundshine and ingestion were predicted to contribute most significantly to the total long-term dose for all regions. The contributions of each exposure pathway and radionuclide show different patterns for certain regions of Japan.

• Journal of the Korea Concrete Institute
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• v.16 no.1 s.79
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• pp.43-53
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• 2004

The current Korean Concrete Design Code(KCI Code) requires the minimum and maximum content of shear s in order to prevent brittle and noneconomic design. However, the required content of the steel reinforcement In KCI Code is quite different to those of the other design codes such as fib-code, Canadian Code, and Japanese Code. Furthermore, since the evaluation equations of the minimum and maximum shear reinforcement for the current KCI Code were based on the experimental results, the equations can not be used for the RC members beyond the experimental application limits. The concrete tensile strength, shear stress, crack inclination, strain perpendicular to the crack, and shear span ratio are strongly related to the lower and upper limits of shear reinforcement. In this research, an evaluation equation for the minimum content of shear reinforcement is theoretical proposed from the Wavier's three principals of the mechanics of materials.

• Journal of the Korea Concrete Institute
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• v.21 no.6
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• pp.719-727
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• 2009

The requirements of the maximum shear reinforcement in the EC2-02 and CSA-04, which are developed based on the truss model, are quite different to those in the ACI-08 code and AIJ-99 code, which are empirical equations. The ACI 318-08, CSA-04, and EC2-02 codes provide an expression for the maximum amount of shear reinforcement ratio as a function of the concrete compressive strength, but Japanese code does not take the influence of the concrete compressive strength into account. For high strength concrete, the maximum amount of shear reinforcement calculated by the EC2-02 and CSA-04 is much greater than that calculated by the ACI 318-08. Ten RC beams having various shear reinforcement ratios were tested and their corresponding shear stress-shear strain curves and failure modes were compared to the predicted ones obtained by the current design codes.

• Nuclear Engineering and Technology
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• v.50 no.2
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• pp.268-279
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• 2018

The ALCYONE multidimensional fuel performance code codeveloped by the CEA, EDF, and AREVA NP within the PLEIADES software environment models the behavior of fuel rods during irradiation in commercial pressurized water reactors (PWRs), power ramps in experimental reactors, or accidental conditions such as loss of coolant accidents or reactivity-initiated accidents (RIAs). As regards the latter case of transient in particular, ALCYONE is intended to predictively simulate the response of a fuel rod by taking account of mechanisms in a way that models the physics as closely as possible, encompassing all possible stages of the transient as well as various fuel/cladding material types and irradiation conditions of interest. On the way to complying with these objectives, ALCYONE development and validation shall include tests on $PWR-UO_2$ fuel rods with advanced claddings such as M5(R) under "low pressure-low temperature" or "high pressure-high temperature" water coolant conditions. This article first presents ALCYONE V1.4 RIA-related features and modeling. It especially focuses on recent developments dedicated on the one hand to nonsteady water heat and mass transport and on the other hand to the modeling of grain boundary cracking-induced fission gas release and swelling. This article then compares some simulations of RIA transients performed on $UO_2$-M5(R) fuel rods in flowing sodium or stagnant water coolant conditions to the relevant experimental results gained from tests performed in either the French CABRI or the Japanese NSRR nuclear transient reactor facilities. It shows in particular to what extent ALCYONE-starting from base irradiation conditions it itself computes-is currently able to handle both the first stage of the transient, namely the pellet-cladding mechanical interaction phase, and the second stage of the transient, should a boiling crisis occur. Areas of improvement are finally discussed with a view to simulating and analyzing further tests to be performed under prototypical PWR conditions within the CABRI International Program. M5(R) is a trademark or a registered trademark of AREVA NP in the USA or other countries.

• Journal of Korean Society of Occupational and Environmental Hygiene
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• v.9 no.1
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• pp.125-155
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• 1999

The objectives of this study were (1) an investigation of the current status of the hazardous substances, (2) a comparative analysis of classification system of hazardous substances between Korea and other countries, (3) a development of the new classification system in Korea, finally a review of prerequisites for effective enforcement of the new system. The results are summarized as follows : 1) The backbone of classification system of hazardous substances in Korea is based on Japanese classification system and EC(European Committee) guideline of hazardous substance. There are many problems in managing and handling of hazardous substances due to discordant of Japanese and EC system. It is desirable to revise the classification system to be harmonized with international guideline for example, guideline of IFCS(The Inter-governmental Forum on Chemical Safety) and EC guideline. 2) There are several problems in definitions of corrosive, sensitizing and irritation in MSDS Code of Ministry of Labour. It is desirable to reform those definitions. 3) Among the hazardous substances under the current system, there are several substances such as, beta-propiolactone, methyl bromide, ethyleneimine, etc that are not used and produced in Korea. It is desirable to exclude the substances from the list of controlled substances. 4) The section 39, about 'substance that designated to attach warning label' in Korea Occupational Safety and Health Act(OSHAct) should be eliminated, because above section is unnecessary under the MSDS system. 5) The researchers recommend to establish a new list of hazardous substance which are controlled by OSHAct. It is desirable that the new list is consist of two types. The first type is 'a list of the specially controlled substances' and the other is 'the generally controlled substances'. 6) It is recommended that the specially controlled substances should include hazardous substances that are highly toxic and widely used in Korea. And the generally controlled substances should include hazardous substances that can be analysed by instrument and carry threshold. limit values(TLV's).

• Journal of the Earthquake Engineering Society of Korea
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• v.1 no.1
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• pp.57-67
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• 1997

The objective of present paper is to investigate elasto-plastic behaviour and estimate the resistance capacity of a beam-shear wall structural system against earthquake ground accleration exciations. Pushover analysis is adopted to estimate inttiate and post stiffnesses and yielding point for inelastic response analysis in LPM (Lumped Parameter Mass) model, and modified Clough model is used as the hysteresis rule of each story. Three earthquake waves are used in the analysis but their peak ground accelerations are changed to be 0.12g, 0.24g. It is assumed that the earthquakes act in the longigtudianl direction of a 25 Story apartment building which consists of two some unit plan. The distribution of story ratio and ductility ratio are estimated and discussed within Korean, Japanese code and UBC.

• Journal of Korean Society of Steel Construction
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• v.16 no.5 s.72
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• pp.661-669
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• 2004

In the steel structure of high-rise buildings, a connection analysisand a column design have been made after welding and bolting suitable gaps. Each country, however, has different codes, and such differences are very big. American steel has been designed according to a code that all axial loads can be carried from the upper parts to the lower parts as determined by the designer, but Korean and Japanese steel have been designed by 1/4 of the standard of all axial loads. In this paper, a metal touch experiment was done as an intermediation parameter with a connecting location and a connecting method for economic and constructive efficiency. Every specimen is tested by a low-to-high displacement control to grasp ultimate strength, displacement, the connection's lateral deflection, and stress. The results of the test were compared and analyzed.

• Journal of the Korean Society of Clothing and Textiles
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• v.41 no.2
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• pp.224-241
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• 2017

This study considered the change process for Western style shoes in Korea during the time of modernization in the 1920s to 1930s. Western style shoes were one of the items imported by foreigners since the Joseon Dynasty and had a significant impact on Korean dress code. It influence started to spread in the 1900s; however, few high level people wore Western shoes until the 1920s. The trend started to spread through newspaper advertisements and news articles after the mid 1920s. Western shoes such as modern girl and modern boy in the 1930s then entered into Korean culture. Korea under Japanese colonial rule was reorganized on a war footing in the latter half of the 1930s and the main materials for western shoes (cow leather, horse leather and sheepskin) were mobilized as materials for war production; subsequently, new materials using rubber were introduced. The representative material is 'Marine Leather (水産皮革)' and Sharkskin 'Gyoheok (鮫革)' and Whaleskin 'Gyeongpi (鯨皮).' Form is like the material has changed over time. This study also observed the flow of westernized Korean modern shoes as well as analyzed the details of materials and shape of western shoes by period. This represent basic materials to understand the legacy of western shoes in the age; in addition, systemic summary is organized by each kind, shape and materials for each style of western shoes.

• Journal of Radiation Protection and Research
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• v.42 no.2
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• pp.130-140
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• 2017

Background: With the need for a domestic level 3 probabilistic safety assessment (PSA), it is essential to develop a Korea-specific code. Health effect assessments study radiation-induced impacts; in particular, long-term health effects are evaluated in terms of cancer risk. The objective of this study was to analyze the latest cancer risk models developed by foreign organizations and to compare the methodology of how they were developed. This paper also provides suggestions regarding the development of Korean cancer risk models. Materials and Methods: A review of cancer risk models was carried out targeting the latest models: the NUREG model (1993), the BEIR VII model (2006), the UNSCEAR model (2006), the ICRP 103 model (2007), and the U.S. EPA model (2011). The methodology of how each model was developed is explained, and the cancer sites, dose and dose rate effectiveness factor (DDREF) and mathematical models are also described in the sections presenting differences among the models. Results and Discussion: The NUREG model was developed by assuming that the risk was proportional to the risk coefficient and dose, while the BEIR VII, UNSCEAR, ICRP, and U.S. EPA models were derived from epidemiological data, principally from Japanese atomic bomb survivors. The risk coefficient does not consider individual characteristics, as the values were calculated in terms of population-averaged cancer risk per unit dose. However, the models derived by epidemiological data are a function of sex, exposure age, and attained age of the exposed individual. Moreover, the methodologies can be used to apply the latest epidemiological data. Therefore, methodologies using epidemiological data should be considered first for developing a Korean cancer risk model, and the cancer sites and DDREF should also be determined based on Korea-specific studies.