• Journal of the Korean Academy of Child and Adolescent Psychiatry
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• 제34권1호
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• pp.4-14
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• 2023

This study aimed to discuss mental health services for children and adolescents that are being implemented as initiatives of the Korean government and to review the functions and roles of these projects during the COVID-19 pandemic. Three government departments are in charge of providing mental health services for children and adolescents: Ministry of Education, Ministry of Gender Equality and Family, and Ministry of Health and Welfare. The Ministry of Education has implemented several policies to facilitate the early detection of mental health issues among school students (from preventive interventions to selective interventions for high-risk students). The Ministry of Gender Equality and Family additionally serves out-of-school children and adolescents by facilitating early identification of adolescents in crises and providing temporary protection or emergency assistance (as required) through the Community Youth Safety-Net Project. Furthermore, the Ministry of Health and Welfare operates relevant mental health agencies for individuals of all ages including children and adolescents. Any high-risk students who have been screened through the projects of the Ministry of Education are supported through referrals to the following institutions for appropriate treatment of their symptoms: specialized hospitals, the Youth Counseling and Welfare Center operated by the Ministry of Gender Equality and Family, the National Youth Healing Center, the Mental Health Welfare Center operated by the Ministry of Health and Welfare, the Suicide Prevention Center, and the Child Welfare Center. To assist students who are facing any psychological difficulties because of the COVID-19 pandemic, the Ministry of Education has established a psychiatric support group for providing emergency mental health care; furthermore, schools are promoting psychological surveillance (e.g., provision of non-face-to-face counseling services that are centered around the Wee Center). The Ministry of Education, Ministry of Gender Equality and Family, and Ministry of Health and Welfare have provided varied mental health support services in order to address the challenges faced by children and adolescents during the pandemic. Nevertheless, the mental health services operated by each ministry do show some limitations because their service provision system is insufficiently collaborative. The present study discussed the positive effects of each initiative as well as its limitations; furthermore, it suggested improvements for facilitating the healthy development of children and adolescents' mental health.

• Nuclear Engineering and Technology
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• 제54권12호
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• pp.4571-4584
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• 2022

The analysis of rapid flow transients in Reactor Coolant Pumps (RCP) is essential for a reactor safety study. An accurate and precise analysis of the RCP coastdown is necessary for the reactor design. The coastdown of RCP affects the coolant temperature and the colloidal crud in the primary coolant. A realistic and kinetic model has been used to investigate the behavior of activated colloidal crud in the primary coolant and steam generator that solves the pump speed analytically. The analytic solution of the non-dimensional flow rate has been determined by the energy ratio β. The kinetic energy of the coolant fluid and the kinetic energy stored in the rotating parts of a pump are two essential parameters in the form of β. Under normal operation, the pump's speed and moment of inertia are constant. However, in a coastdown situation, kinetic damping in the interval has been implemented. A dynamic model ACCP-SMART has been developed for System Integrated Modular and Advanced Reactor (SMART) to investigate the corrosion due to activated colloidal crud. The Fickian diffusion model has been implemented as the reference corrosion model for the constituent component of the primary loop of the SMART reactor. The activated colloidal crud activity in the primary coolant and steam generator of the SMART reactor has been studied for different equilibrium corrosion rates, linear increase in corrosion rate, and dynamic RCP coastdown situation energy ratio b. The coolant specific activity of SMART reactor equilibrium corrosion (4.0 mg s^-1) has been found 9.63×10^-3 µCi cm^-3, 3.53×10^-3 µC cm^-3, 2.39×10^-2 µC cm^-3, 8.10×10^-3 µC cm^-3, 6.77× 10^-3 µC cm^-3, 4.95×10^-4 µC cm^-3, 1.19×10^-3 µC cm^-3, and 7.87×10^-4 µC cm^-3 for ²⁴Na, ⁵⁴Mn, ⁵⁶Mn, ⁵⁹Fe, ⁵⁸Co, ⁶⁰Co, ⁹⁹Mo, and ⁵¹Cr which are 14.95%, 5.48%, 37.08%, 12.57%, 10.51%, 0.77%, 18.50%, and 0.12% respectively. For linear and exponential coastdown with a constant corrosion rate, the total coolant and steam generator activity approaches a higher saturation value than the normal values. The coolant and steam generator activity changes considerably with kinetic corrosion rate, equilibrium corrosion, growth of corrosion rate (ΔC/Δt), and RCP coastdown situations. The effect of the RCP coastdown on the specific activity of the steam generators is smeared by linearly rising corrosion rates, equilibrium corrosion, and rapid coasting down of the RCP. However, the time taken to reach the saturation activity is also influenced by the slope of corrosion rate, coastdown situation, equilibrium corrosion rate, and energy ratio β.

• 중소기업연구
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• 제41권4호
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• pp.65-86
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• 2019

본 연구는 창업이 더욱 장려되는 상황에서 기업가정신과 창업실패두려움의 구성요소들이 창업의지에 서로 어떻게 영향을 주는 지에 대해 실증 분석하였다. 특히, 창업실패두려움을 세 가지 하위변수(재무적 손실, 심리적 손실, 경력 손실 각각에 대한 두려움)로 구분하여 조절효과를 검증하였다. 연구결과 기업가정신 중 진취성과 위험감수성은 창업의지에 정(+)의 영향을 주는 것으로 나타났으나, 혁신성은 영향이 없는 것으로 나타났다. 기업가정신이 창업의지에 미치는 영향 관계에서 창업실패두려움은 하위변수 모두 통계적으로 유의한 조절효과가 없는 것으로 나타나 창업실패두려움은 창업의지에 독립변수로서 부(-)의 영향을 미치는 것으로 보인다. 하지만 창업실패두려움과 기업가정신의 하위변수들 각각의 상호작용항에 따라 회귀계수값(β)이 양(+)의 값이 되기도 하고 음(-)의 값이 되는 것을 볼 때 창업실패두려움의 종류에 따라 조절효과는 긍정적일 수도 있고 부정적일 수도 있음을 추론하게 한다. 이상의 연구결과를 토대로 창업 활성화를 위해서는 기업가정신을 고취하고 실패에 대한 두려움을 낮출 수 있는 정교한 창업 교육 프로그램이 필요하며 동시에 창업 실패에 대한 두려움을 낮출 수 있는 사회적 안전망 구축 방안이 마련될 필요가 있다.

• Nuclear Engineering and Technology
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• 제55권5호
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• pp.1802-1813
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• 2023

Conjugate heat transfer between liquid metal and solid is a common phenomenon in a liquid-metal-cooled fast reactor's fuel assembly and heat exchanger, dramatically affecting the reactor's safety and economy. Therefore, comprehensively studying the sophisticated conjugate heat transfer in a liquid-metal-cooled fast reactor is profound. However, it has been evidenced that the traditional Simple Gradient Diffusion Hypothesis (SGDH), assuming a constant turbulent Prandtl number (Pr_t,, usually 0.85 - 1.0), is inappropriate in the Computational Fluid Dynamics (CFD) simulations of liquid metal. In recent decades, numerous studies have been performed on the four-equation model, which is expected to improve the precision of liquid metal's CFD simulations but has not been introduced into the conjugate heat transfer calculation between liquid metal and solid. Consequently, a four-equation model, consisting of the Abe k - ε turbulence model and the Manservisi k_𝜃 - ε_𝜃 heat transfer model, is applied to study the conjugate heat transfer concerning liquid metal in the present work. To verify the numerical validity of the four-equation model used in the conjugate heat transfer simulations, we reproduce Johnson's experiments of the liquid lead-bismuth-cooled turbulent pipe flow using the four-equation model and the traditional SGDH model. The simulation results obtained with different models are compared with the available experimental data, revealing that the relative errors of the local Nusselt number and mean heat transfer coefficient obtained with the four-equation model are considerably reduced compared with the SGDH model. Then, the thermal-hydraulic characteristics of liquid metal turbulent pipe flow obtained with the four-equation model are analyzed. Moreover, the impact of the turbulence model used in the four-equation model on overall simulation performance is investigated. At last, the effectiveness of the four-equation model in the CFD simulations of liquid sodium conjugate heat transfer is assessed. This paper mainly proves that it is feasible to use the four-equation model in the study of liquid metal conjugate heat transfer and provides a reference for the research of conjugate heat transfer in a liquid-metal-cooled fast reactor.

• 한국노년학
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• 제39권2호
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• pp.325-345
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• 2019

본 연구의 목적은 사회적으로 고립된 남성 독거노인의 생애사적 접근을 통해 사회적으로 고립되기까지의 과정과 삶을 심도 있게 이해하기 위한 탐색적 연구이다. 연구방법으로는 질적연구 생애사 방법의 하나인 'Mandelbaum(1973)의 삶의 영역(Dimensions), 전환점(turnings), 적응(adaptation)'이라는 개념틀로 분석하였다. 본 연구결과에 따르면, 사회적으로 고립된 노인들은 가족 관계 단절, 빈곤, 열악한 일자리, 건강악화 등의 복합적인 어려움을 경험하면서 사회적으로 고립된 것으로 나타났다. 구체적으로 삶의 영역에서 고립 전의 원가족과의 삶에서 부모와의 원만하지 못한 관계나 부재, 가족의 빈곤, 주위 사람들과의 원만하지 못한 관계 등의 경험이 있었다. 노동시장에서 막노동, 배달, 장사, 허드렛일 등의 좋지 않은 일자리를 갖고 있었다. 전환점의 영역에서는 외환위기, 부모의 이혼과 죽음, 배우자 외도, 경제적 어려움 등의 여러 원인으로 원가족과 배우자와의 분리로 인한 가족과의 단절을 경험하게 되었다. 적응의 영역에서 참여자들은 삶의 각 전환점에서 변화된 삶을 받아들이며 자신의 역할을 수행하면서 타협하고 절충하면서 적절히 적응하려는 노력을 해나가고 있었다. 국민기초수급자라는 사회적 안전망 제도에 들어왔고 그 안전망을 지키기 위해 한곳에 머무르는 지금의 삶이 더 안정적인 삶을 살게 만들었으며 개인적인 취미생활과 네트워크를 통한 대리만족으로 적응하고 있음을 밝혔다. 이는 기존연구에서 고립된 노인들이 우울증과 고독사의 위험에 심하게 노출되었다는 연구결과와 다소 다른 결과이다. 하지만 상대적으로 고립감이 낮은 노인을 인터뷰한 본 연구의 특성을 동시에 감안해야 할 것이다. 이 같은 연구 결과를 바탕으로 여러 실천적 정책적 함의를 제시했다.

• Nuclear Engineering and Technology
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• 제55권10호
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• pp.3913-3923
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• 2023

Todays, medium energy resolution detectors are preferably used in radioisotope identification devices(RID) in nuclear and radioactive material categorization. However, there is still a need to develop or enhance « automated identifiers » for the useful RID algorithms. To decide whether any material is SNM or NORM, a key parameter is the better energy resolution of the detector. Although masking, shielding and gain shift/stabilization and other affecting parameters on site are also important for successful operations, the suitability of the RID algorithm is also a critical point to enhance the identification reliability while extracting the features from the spectral analysis. In this study, a RID algorithm based on Bayesian statistical method has been modified for medium energy resolution detectors and applied to the uranium gamma-ray spectra taken by a LaBr3:Ce detector. The present Bayesian RID algorithm covers up to 2000 keV energy range. It uses the peak centroids, the peak areas from the measured gamma-ray spectra. The extraction features are derived from the peak-based Bayesian classifiers to estimate a posterior probability for each isotope in the ANSI library. The program operations were tested under a MATLAB platform. The present peak based Bayesian RID algorithm was validated by using single isotopes(²⁴¹Am, ⁵⁷Co, ¹³⁷Cs, ⁵⁴Mn, ⁶⁰Co), and then applied to five standard nuclear materials(0.32-4.51% at.²³⁵U), as well as natural U- and Th-ores. The ID performance of the RID algorithm was quantified in terms of F-score for each isotope. The posterior probability is calculated to be 54.5-74.4% for ²³⁸U and 4.7-10.5% for ²³⁵U in EC-NRM171 uranium materials. For the case of the more complex gamma-ray spectra from CRMs, the total scoring (ST) method was preferred for its ID performance evaluation. It was shown that the present peak based Bayesian RID algorithm can be applied to identify ²³⁵U and ²³⁸U isotopes in LEU or natural U-Th samples if a medium energy resolution detector is was in the measurements.

• Korean Chemical Engineering Research
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• 제61권4호
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• pp.496-504
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• 2023

세계 각국은 지구온난화로 인한 피해가 증가함에 따라 화석연료를 대신해 탄소배출 없이 지속 가능하게 이용할 수 있는 새로운 에너지 자원들을 찾기 위하여 노력하고 있다. 전세계적으로 4차 산업이 고도화되며 전력수요가 급증했고, 상승하는 수요를 충족함과 동시에 온실가스 배출을 줄이기 위해 탄소비중이 적거나 없는 에너지원을 이용해 안정적인 전력수급계통을 확보하려는 움직임이 커지고 있다. 본 총설에서는 해외 탄소중립 시나리오와 화력발전 잔존여부에 따라 2가지 시나리오인 혁신, 안전으로 분류하여 정부의 탄소저감 목표를 비교 및 분석하였다. 또한, 국내 시나리오의 경우10차 전력수급기본계획의 전력수요 전망 및 온실가스 배출 현황을 연계하여 이를 토대로 탄소저감의 주축이 되는 에너지 분야인 전환, 수소, 수송, 탄소포집 및 활용 부문에서의 핵심 기술 동향 및 정부 주도의 정책흐름을 정리하여 탄소중립기술의 현황을 기술했다. 또한, 해외 시나리오 분석에서 시사되었던 에너지 분야의 주요 변화를 반영하여 국내 탄소저감 전략의 방향을 제시하였다.

• 인터넷정보학회논문지
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• 제24권6호
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• pp.91-98
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• 2023

오늘날 인공지능 산업이 발전함에 따라 여러 분야에 걸쳐 인공지능을 통한 자동화 및 최적화가 이루어지고 있다. 국내의 철도 분야 또한 지도 학습을 이용한 레일의 결함을 검출하는 연구들을 확인할 수 있다. 그러나 철도에는 레일만이 아닌 다른 구조물들이 존재하며 그중 선로 체결 장치는 레일을 다른 구조물에 결합시켜주는 역할을 하는 장치로 안전사고의 예방을 위해서 주기적인 점검이 필요하다. 본 논문에는 선로 체결 장치의 데이터를 이용하여 준지도 학습(semi-supervised learning)과 전이 학습(transfer learning)을 이용한 분류기를 학습시켜 선로 안전 점검에 사용되는 비용을 줄이는 방안을 제안한다. 사용된 네트워크는 Resnet50이며 imagenet으로 선행 학습된 모델이다. 레이블이 없는 데이터에서 무작위로 데이터를 선정 후 레이블을 부여한 뒤 이를 통해 모델을 학습한다. 학습된 모델의 이용하여 남은 데이터를 예측 후 예측한 데이터 중 클래스 별 확률이 가장 높은 데이터를 정해진 크기만큼 훈련용 데이터에 추가하는 방식을 채택하였다. 추가적으로 초기의 레이블된 데이터의 크기가 끼치는 영향력을 확인해보기 위한 실험을 진행하였다. 실험 결과 최대 92%의 정확도를 얻을 수 있었으며 이는 지도 학습 대비 5% 내외의 성능 차이를 가진다. 이는 제안한 방안을 통해 추가적인 레이블링 과정 없이 비교적 적은 레이블을 이용하여 분류기의 성능을 기존보다 향상시킬 수 있을 것으로 예상된다.

• Nuclear Engineering and Technology
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• 제55권10호
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• pp.3543-3548
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• 2023

Shutdown chemistry evolution is performed in nuclear power plants at each refueling outage (RFO) to establish safe conditions to open system and minimize inventory of corrosion products in the reactor coolant system (RCS). After hydrogen peroxide is added to RCS during shutdown chemistry evolution, corrosion products are released and are removed by filters and ion exchange resins in the chemical volume control system (CVCS). Shutdown chemistry evolution including RCS clean-up time to remove released corrosion products impacts the critical path schedule during RFOs. The estimation of clean-up time prior to RFO can provide more reliable actions for RCS clean-up operations and transients to operators during shutdown chemistry. Electric Power Research Institute (EPRI) shutdown calculator (SDC) enables to provide clean-up time by Co-58 peak activity through operational data from nuclear power plants (NPPs). In this study, we have investigated the results of EPRI SDC by shutdown chemistry data of Co-58 activity using NPP data from previous cycles and modeled the estimated clean-up time by EPRI SDC using average Co-58 activity of the NPP. We selected two RFO data from the NPP to evaluate EPRI SDC results using the purification time to reach to 1.3 mCi/cc of Co-58 after hydrogen peroxide addition. Comparing two RFO data, the similar purification time between actual and computed data by EPRI SDC, 0.92 and 1.74 h respectively, was observed with the deviation of 3.7-7.2%. As the modeling the estimated clean-up time, we calculated average Co-58 peak concentration for normal cycles after cycle 10 and applied two-sigma (2σ, 95.4%) for predicted Co-58 peak concentration as upper and lower values compared to the average data. For the verification of modeling, shutdown chemistry data for RFO 17 was used. Predicted RCS clean-up time with lower and upper values was between 21.05 and 27.58 h, and clean-up time for RFO 17 was 24.75 h, within the predicted time band. Therefore, our calculated modeling band was validated. This approach can be identified that the advantage of the modeling for clean-up time with SDC is that the primary prediction of shutdown chemistry plans can be performed more reliably during shutdown chemistry. This research can contribute to improving the efficiency and safety of shutdown chemistry evolution in nuclear power plants.

• Nuclear Engineering and Technology
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• 제55권11호
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• pp.3940-3955
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• 2023

A new method of numerical simulating prediction and decontamination effect evaluation for abrasive jet decontamination to radioactively contaminated metal is proposed. Based on the Computational Fluid Dynamics and Discrete Element Model (CFD-DEM) coupled simulation model, the motion patterns and distribution of abrasives can be predicted, and the decontamination effect can be evaluated by image processing and recognition technology. The impact of three key parameters (impact distance, inlet pressure, abrasive mass flow rate) on the decontamination effect is revealed. Moreover, here are experiments of reliability verification to decontamination effect and numerical simulation methods that has been conducted. The results show that: ⁶⁰Co and other homogeneous solid solution radioactive pollutants can be removed by abrasive jet, and the average removal rate of Co exceeds 80%. It is reliable for the proposed numerical simulation and evaluation method because of the well goodness of fit between predicted value and actual values: The predicted values and actual values of the abrasive distribution diameter are Ф57 and Ф55; the total coverage rate is 26.42% and 23.50%; the average impact velocity is 81.73 m/s and 78.00 m/s. Further analysis shows that the impact distance has a significant impact on the distribution of abrasive particles on the target surface, the coverage rate of the core area increases at first, and then decreases with the increase of the impact distance of the nozzle, which reach a maximum of 14.44% at 300 mm. It is recommended to set the impact distance around 300 mm, because at this time the core area coverage of the abrasive is the largest and the impact velocity is stable at the highest speed of 81.94 m/s. The impact of the nozzle inlet pressure on the decontamination effect mainly affects the impact kinetic energy of the abrasive and has little impact on the distribution. The greater the inlet pressure, the greater the impact kinetic energy, and the stronger the decontamination ability of the abrasive. But in return, the energy consumption is higher, too. For the decontamination of radioactively contaminated metals, it is recommended to set the inlet pressure of the nozzle at around 0.6 MPa. Because most of the Co elements can be removed under this pressure. Increasing the mass and flow of abrasives appropriately can enhance the decontamination effectiveness. The total mass of abrasives per unit decontamination area is suggested to be 50 g because the core area coverage rate of the abrasive is relatively large under this condition; and the nozzle wear extent is acceptable.