• 한국보건간호학회지
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• 제29권3호
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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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• 제51권3호
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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.

• 콘크리트학회논문집
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• 제16권1호
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• pp.43-53
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• 2004

철근콘크리트 부재가 취성적이며 국부적으로 파괴되지 않도록 하기 위하여 각 기준식에서는 철근콘크리트 부재의 최소전단 보강근비를 요구하고 있다. 우리나라에서 현재 사용되고 있는 철근콘크리트 구조설계기준의 최소전단철근비에 대한 기준식과 캐나다 기준식, 유럽 기준식, 일본건축학회 기준식을 비교하면 각 기준식에 의하여 계산된 최소전단보강근비 값에는 많은 차이가 있어 그 신뢰성에 의문을 갖게 한다. 즉, 동일한 콘크리트의 실린더 압축강도에 대하여 각 기준식의 최소전단보강근비 값은 최대 2배 이상의 차이가 있다. 또한, 최소전단보강근비에 영향을 주는 요소가 각 기준식마다 다르며, 이에 대한 연구도 그 중요성에 비하여 극히 적은 실정이다. 이연구에서는 트러스 모델에 근거한 이론적인 방법에 의하여 철근콘크리트 부재의 최소전단보강근비를 예측하였다. 제안식에는 최소전단철근비에 영향을 주는 콘크리트의 압축강도, 전단보강근의 항복응력, 주근비, 전단경간비의 영향이 고려되었다. 제안식에 의하여 계산된 최소전단철근비는 콘크리트 압축강도에 따라 변화하며, ACI 318-02 및 캐나다 규준과 비슷한 분포를 나타냈다. KCI-99 및 ACI 318-02의 최소전단철근비는 주인장철근비에 관계없이 일정하지만 제안식에 의한 최소전단철근비는 주인장철근비가 증가할수록 줄어드는 양상을 보였다. 또한, 전단경간비에 따른 최소전단철근비에 대하여 KCI-99 및 ACI-318-02에 의한 최소전단철근비는 전단경간비에 관계없이 일정한 값을 보였지만 제안식에 의한 최소전단철근비는 전단경간비가 증가할수록 증가하는 양상을 보였다.변화로 인한 resetup의 번거러움을 줄일 수 있었고 환자에게 인위적으로 치료 자세를 유지해야하는 불편함을 해소할 수 있었다. 궁극적으로는 set-up의 재현성을 유지해 보다 정확한 치료를 가능하게 했고 앞으로 이 고정용구를 보완, 개선시켜서 환자의 치료에 활용한다면 더욱더 질적으로 향상된 치료를 제공 할 수 있을 것으로 사료된다.하였다. IV. 결론 Forward IMRT는 2차원적인 치료법에 비하여 PTV에는 균일한 선량분포를 이루면서 정상조직에는 tolerance dose 이하로 선량을 전달 할 수 있는 치료기법이었다. 계속적으로 평가할 필요가 있을 것이다.> 최대 $11.65\%$까지 골조직에 의한 선량감소가 나타나는 것을 알 수가 있다. 또한, Diode detector로 측정한 심부선량 값은 두부, 경부, 대퇴부, 슬관절, 족관절에서 각각 $95.23{\pm}1.18,\;98.33{\pm}0.6,\;93.5{\pm}1.5,\;87.3{\pm}1.5,\;86.90{\pm}1.16$으로 나타났으며, TLD로 측정한 대퇴부, 슬관절, 족관절에서의 표면선량과 비교했을 때 부위에 따라 최소 $4.53\%{\sim}$ 최대 $12.6\%$ 까지 차이를 보였다. 그리고 골조직에 의한 선량감쇄의 영향이 적은 복부(배꼽)에서는 열형광선량계 및 다이로드측정기로 측정한 값이 각각 $101.58{\pm}0.95,\;104.77{\pm}1.18$로 큰 차이가 없었다. IV 결론 전신방사선조사시 표면선량을

• 콘크리트학회논문집
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• 제21권6호
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• pp.719-727
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• 2009

변환각트러스모델에 근거한 EC2-02 기준식이나 CSA-04 기준식의 최대 전단보강철근비는 반경험적 방법에 근거한 ACI 318-08 기준식이나 AIJ-99 기준식에서 요구하는 최대 전단보강철근비와 많은 차이가 있다. ACI 318-08 기준식, CSA-04 기준식 및 EC2-02 기준식은 콘크리트의 압축강도에 따라서 최대 전단보강철근비가 증가하지만 AIJ-99 기준식은 일정한 값이 적용된다. 고강도콘크리트에 대하여 EC2-02 기준식이나 CSA-04 기준식이 요구하는 최대 전단보강철근비는 ACI 318-08 기준식이 요구하는 최대 철근비에 비하여 매우 크다. 이 연구에서는 10개의 철근콘크리트 보 실험을 통하여 전단보강철근의 양과 콘크리트의 압축강도가 최대 전단보강철근비에 미치는 영향을 파악하였다. 실험에 의하면 ACI 318-08 기준식이나 AIJ-99 기준식에서 요구하는 최대 전단보강철근비보다 최대 약 1.9배까지 전단보강철근을 많이 배근하였음에도 불구하고 실험 결과는 전단보강철근이 항복한 이후에 부재가 최대 내력에 도달하였다.

• Nuclear Engineering and Technology
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• 제50권2호
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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.

• 한국산업보건학회지
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• 제9권1호
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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).

• 한국지진공학회논문집
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• 제1권1호
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• pp.57-67
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• 1997

본 논문의 목적은 보-전단벽식 고층아파트의 단소성 지진응답해석을 수행하여 내진성능을 검토하는 것이다. 이를 위해 우선 구조물을 3차원 입체모델화하여 정적 탄소성해석을 수행하고 층 강성을 평가한 후, 그 결과를 이용하여 집중질량계모델을 사용한 시간이력 응답해석을 수행한다. 이때 탄소성 이력모델로는 modified Clough 모델을, 입력하중으로는 3종류의 기록 지진동 El-Centro 1940 NS, Taft 1952 EW, Hachinohe 1968 NS를 사용하되, 최대 지반가속도를 0.12g, 0.24g로 조절하여 사용한다. 해석모델로 장변 방향을 배치된 전단벽의 단면적이 단변의 0.5배이고, 동일한 평면을 가진 2세대가 일자형으로 배치된 25층의 아파트를 선정한다. 층간 변형각, 소성율등을 구하고 우리나라 및 미국, 일본의 내진규준에서 정하고 있는 제한사항과 비교검토한다.

• 한국강구조학회 논문집
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• 제16권5호통권72호
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• pp.661-669
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• 2004

철골구조에 있어서 기둥 이음부의 설계는 단순히 적당한 틈에 용접이나 볼트에 의한 이음으로 해석 및 설계가 이루어지고 있는 것이 보편적인 현실이다. 이때 이음부에서 메탈터치에 의하여 상부의 응력을 하부로 전달하는 정도를 규정하는 기준은 각 나라마다 다르다. 미국은 설계자의 판단에 따라 모두 전달 가능하다는 규정아래 설계가 이루어지고 있으며, 우리나라와 일본의 경우는 25%까지 전달 가능하다는 규준에 의해 설계가 이루어지고 있어 그 차이가 너무 크다. 따라서 본 연구에서는 메탈터치에 의한 이음의 응력체계를 규명하여 이음의 합리성을 증진시키고, 이음의 경제성 및 시공성을 위해 틈의 위치 및 이음방법을 매개변수로 하여 메탈터치 실험을 실시하여 미국 및 일본 규준과 비교하였다. 또한 메탈터치 이음부의 거동을 실험적인 방법과 해석적인 방법을 통하여 분석하여 메탈터치 이음부의 설계에 필요한 기초 자료를 제공하고자 한다.

• 한국의류학회지
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• 제41권2호
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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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• 제42권2호
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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.