본 연구는 고온 환경에서 사료내 트립토판과 나이아신의 첨가가 산란계의 생산성, 난품질, 지방간 지표 및 혈액성상에 미치는 상호작용 효과를 조사하고자 수행되었다. 총 384수의 25주령 로만 갈색종 산란계를 4처리 8반복으로 반복당 12수씩 무작위 임의 배치하였다. 기본 사료는 트립토판과 나이아신의 추가적인 첨가는 없으며 모든 영양소 및 에너지는 로만갈색종 산란계의 요구량에 충족하거나 초과하도록 배합되었다. 사료 처리구는 2 × 2 요인 실험 설계법으로 두 가지 수준의 트립토판(0 및 0.16%)과 두 가지 수준의 나이아신(0 및 0.03%)이 포함되었다. 모든 산란계의 사양환경은 일반 농가에서 낮시간에 온도가 올라가는 점을 고려하여 일일 중 8시간은 온도 31.4 ± 1.17℃, 습도 86.0 ± 4.28%으로 설정하였으며, 나머지 16시간은 온도 26.7 ± 1.10℃, 습도 61.7 ± 6.34%로 유지하여 주기적인 고온 환경을 조성하였다. 실험은 10주간 진행되었다. 실험 결과 사료내 트립토판과 나이아신의 주요 효과와 상호작용은 나타나지 않았다. 이와 유사하게, 난각 강도, 난각 두께, 난각색, 난황색 및 호우유닛에 대한 상호작용 도 나타나지 않았다. 주요 효과로 0.03%의 나이아신 첨가는 난황색을 유의적으로 감소시켰으나 호우유닛은 유의적으로 증가시켰다. 하지만, 0.16%의 트립토판 첨가는 난품질에 영향을 끼치지 않았다. 지방간 지표와 혈액성상에서 사료내 트립토판과 나이아신의 주요 효과 및 상호작용은 나타나지 않았다. 결론적으로, 본 연구에서 설정한 농도의 사료내 트립토판과 나이아신의 첨가는 고온 환경에서 사양되는 산란계의 생산성, 난품질, 지방간 지표 및 혈액성상에 긍정적인 영향을 미치지 않았다.

본 연구는 조직구성원들의 긍정심리자본 개발 및 조직의 리더육성을 위한 긍정리더십 역량 측정도구를 개발하고 타당화하는데 있다. 이를 위해 선행연구에서 제시된 긍정리더십 역량모형을 바탕으로 후속 연 구를 진행하여 타당성이 확보된 측정도구를 개발하였다. 연구 절차는 DeVellis의 척도 개발 절차를 적용 하여 예비문항 개발 및 검증, 측정도구 검증 단계를 거쳐 타당성을 확보하였다. 주요 연구결과는 다음과 같다. 첫째, 선행연구에서 제시된 3대 영역, 9개의 긍정리더십역량 구성요인의 측정도구로 사용할 예비문항을 개발하여 검증한 결과 41개 문항으로 구성되었다. 둘째, 측정도구 타당성 확보를 위해 탐색적 요인분석과 확인적 요인분석을 실시한 결과 요인적재량 기준에 미치지 못한 문항이 삭제되었고, 유사한 개념끼리 통합되어 3대 영역, 7개의 긍정리더십 역량 요인, 24개 측정 문항으로 구성 되었다. 이후 공인타당성, 측정동일성 검증, 동일방법편의 검증의 과정을 거쳐 최종 확정된 긍정 리더십역량 측정도구는 개인영역은 자기인식, 긍정적 자기관리, 솔선수범 등 9문항, 관계영역은 구성원 존중, 구 성원 이해 등 8문항, 조직영역은 구성원 개발, 구성원 성과관리 등 7문항으로 총 24개 문항으로 구성되었다. 본 연구는 최근 변화되는 경영환경속에서 긍정리더십 역량 측정도구를 타당화하였다는 점에서 학문적 의의가 있으며, HRD 현장에 긍정리더십 역량을 측정하고 그 결과를 바탕으로 인적자원관리에 활용될 수 있다는 점에서 실천적 의의가 있다.

본 연구에서는 형광측정기법을 사용하여 태안반도 인근 8지점의 표층 해수 내 미세플라스틱 정량분포를 조사하였다. 연구결과 미세플라스틱의 검출범위는 0~360.5 particles/l (평균 149.7 ± 46.0 particles/l)로 나타났다. 하지만 해양환경 내 미세플라스틱의 정량분석방법이 표준화되지 않아 타 연구결과와 직접비교 하는 것이 불가능한 상황이다. 본 연구결과 검출된 미세플라스 틱을 크기별로 분류하면 < 50 μm 크기가 우점하지만, St. 3의 경우 > 500 μm이 25.6%를 차 지하여 지역별로 우점하는 미세플라스틱의 크기에 차이가 나타난다. 또한 채집지역, 저질의 종 류, 검출되는 플라스틱 크기에 따른 미세플라스틱의 검출량 비교에도 뚜렷한 상관관계를 가지 는 요인을 확인할 수 없었다. 이는 플라스틱의 재질에 따른 물리 · 화학적 특성, 해양의 동적 조건(해류, 바람, 파도, 조류 등), 지질학적 특성(지형, 경사 등), 연안 생물을 포함한 저질의 구성 및 특성, 상호작용, 인간활동(어업, 개발, 관광 등), 기상조건(홍수, 강우 등)과 같은 다양한 요인 이 미세플라스틱의 거동에 영향을 주기 때문이다. 그러므로 향후 정량분석방법 표준화 및 환 경요인에 대한 분석이 수반된 미세플라스틱 모니터링 기초연구가 필요한 상황이다.

본 연구에서는 무인항공기인 드론을 활용한 VDMS(Vision-based Displacement Measurement System)를 통해 동적변위계측 정 확도와 동특성 추정 신뢰성 검증을 위한 동적실험을 실시하였다. 비행하는 드론의 이동 및 회전진동을 보정하기 위해 영상 내부의 변 위가 발생하지 않는 고정점을 활용한 보정밥법을 사용하였으며, 검증을 위해 설치한 범용 센서인 LVDT와 LDS의 변위계측 결과와 비 교하여 그 오차를 시간영역과 진동수영역에서 분석하였다. 3가지 타입의 장비 모두 최대 변위 도달 및 주기 운동 계측에 있어서 대체 적으로 유사한 결과를 나타내었다. LDS 기준의 오차 분석 결과, 드론과 LVDT는 가진 진동수 변화에 의한 오차 값은 미비하나, 최대 발생 변위가 작을수록 오차 값은 증가하였다.

구조물의 안정성 및 이상 징후 판단에 있어 균열의 발생 여부와 진전 정도는 가장 기본적인 조사 항목이다. 본 연구 에서는 일반적인 스마트폰을 통해 균열 이미지를 촬영하고 이로 부터 균열 검출과 크기를 산정하는 균열 분석 시스템을 개발하 였다. 모폴로지 기법을 적용하되 투영변환 및 3차회선 보간, 히스토그램 기반의 명도 입계값 산정 기법을 적용함으로서 이미지 보정과 노이즈 제거 과정을 통한 효과적 균열 검출이 가능하였다. ArUco 마커를 통해 손쉽고 경제적인 균열 크기 산정이 가능 하였으며, 스마트폰 앱과 클라우드 서버 기반의 이원화 분석시스템을 통해 손쉬운 현장 적용성 및 처리 시간 단축, 세부 균열의 추적관리 가능성을 확인하였다. 개발 시스템을 이용한 실내 성능 평가를 수행한 결과, 균열 측정 오차는 0.03㎜ 미만으로 나타 났으며 조건별 다수 측정 결과에서 높은 재현성이 확인되었던바, 개발된 균열 분석 시스템의 정확성 및 현장 적용성을 예상할 수 있었다.

The rational evaluation of carbon-based conductive ink performance is critical to both industrial production and applications. Herein, a model to evaluate writing performance of conductive ink by line resistance was proposed by investigating possible relations among different parameters and establishing relevant model to estimate ink writing performance. Bulk conductive inks were prepared and characterized to provide samples for model. To improve the precision of model, the impact of external factors including writing speed and angle was studied. Nonlinear regression and back propagation artificial neural network were employed to estimate line resistance, and cross check validation was conducted to prove robustness and precision of model. Most importantly, the investigation will open up a new path for the exploration of other carbon-based handwritten electronic devices.

When self-disposing of radioactive waste, it is important to follow the acceptable concentration standards for each nuclide set by the Nuclear Safety and Security Commission (NSSC). Gamma-emitting nuclides can be easily analyzed with a simple pretreatment process, but beta-emitting nuclides require a chemical separation procedure to be analyzed for radiochemistry analysis. When analyzing betaemitting nuclides for the purpose of self-disposal, there may be difficulties in radiation detection after the chemical separation process. This is because the concentration of beta nuclides in the sample may be low and some of them may be lost during the chemical separation. Therefore, measurement method of gross-beta activity can be used instead of that of each nuclide to access the compliance of selfdisposal criteria. While a proportional counter is commonly used to measure gross-beta activity, liquid scintillation counting can also be used to measure gross-beta, and we plan to compare the results of both methods.

Measurement of oxide ion (O2-) concentration is a basic technology required in molten salt fields, from energy storage systems to electrolytic reduction of rare earth elements or spent nuclear fuels. In a molten salt reactor, O2- ions react with actinide elements to form their oxides or oxy-chlorides to induce actinide precipitation, and promote metal corrosion to cause a failure of structural material. For these reasons, removal of O2- ions and monitoring of the O2- concentration in molten salt reactors are essential. In this study, methods using chemical and electrochemical methods were investigated for measuring the concentration of O2- ions in a molten salts. The acid-base neutralization reaction was used as a chemical analysis method. And electrochemical methods using the O2- diffusion limit current and YSZ (yttria stabilized zirconia) indicator electrode were used for measuring the O2- concentration. Finally, a modified method using porous membrane electrode was applied to monitor the O2- concentration. The O2- concentration was measured up to about 2wt% of Li2O by the method using the O2- diffusion current, up to about 4wt% by the YSZ indicator electrode, and about 6wt% by the porous membrane electrode in LiCl molten salts.

According to ISO 4037, the thickness of the inherent filtration for the radiation qualities L-40 to L- 240, N-40 to N-400, W-60 to W-300 and H-80 to H-400 shall be equivalent to 4 mm Al for matched reference radiation fields or adjusted as far as possible to 4 mm Al for characterized reference radiation fields. And for matched reference fields, the tube window must be made of beryllium and its thickness should not exceed 10 mm. In the case of characterized reference fields, the thickness of the beryllium window should not exceed 10 mm, but it is acceptable to use an aluminum window with a maximum thickness of 1.5 mm. 320 KV X-ray tube installed at KHNP-CRI has been designed to equipped with a 3 mm Be for tube window and an additional 4 mm Al to obtain a total inherent filtration equivalent to that of 4 mm Al. In the previous study, the inherent filtration of 320 kV X-ray tube at KHNP-CRI has been verified by MCNP simulation. However, the ISO standards suggest a method for determining the thickness of the inherent filtration by half-value layer (HVL) measurement and spectrometry. In this regard, the inherent filtration was reassessed using HVL measurement. To determine the inherent filtration, 1st HVL of the beam generated by the tube at a tube potential 60 kV was measured. The measurements were conducted with a calibrated spherical ionization chamber (model A3, Exradine) placed at a distance of 1 m from the target, at the center of the radiation field size. The X-ray tube current was set to 2 mA. The thickness of aluminum absorbers was gradually adjusted in subsequent measurements until approached the 1st HVL. 1st HVL were estimated using the linear regression equation computed with the current values for the thickness of the absorbers. As a results, the thickness of the 1st HVL was estimated as 2.845 mm Al. According to the correlation between the inherent filtration and 1st HVL suggested in ISO standard, the value of the inherent filtration was deduced as 4.25 mm Al that is rounded to the nearest 0.05 mm by interpolation. Further studies on the effects of the inherent filtration thickness determined in this study will be conducted.

Our research team has developed a gamma ray detector which can be distributed over large area through air transport. Multiple detectors (9 devices per 1 set) are distributed to measure environmental radiation, and information such as the activity and location of the radiation source can be inferred using the measured data. Generally, radiation is usually measured by pointing the detector towards the radioactive sources for efficient measurement. However, the detector developed in this study is placed on the ground by dropping from the drone. Thus, it does not always face toward the radiation source. Also, since it is a remote measurement system, the user cannot know the angle information between the source and detector. Without the angle information, it is impossible to correct the measured value. The most problematic feature is when the backside of the detector (opposite of the scintillator) faces the radiation source. It was confirmed that the measurement value decreased by approximately 50% when the backside of the detector was facing towards the radiation source. To calibrate the measured value, we need the information that can indicate which part of the detector (front, side, back) faces the source. Therefore, in this study, we installed a small gamma sensor on the backside of the detector to find the direction of the detector. Since this sensor has different measurement specifications from the main sensor in terms of the area, type, efficiency and measurement method, the measured values between the two sensors are different. Therefore, we only extract approximate direction using the variation in the measured value ratio of the two sensors. In this study, to verify the applicability of the detector structure and measurement method, the ratio of measured values that change according to the direction of the source was investigated through MCNP simulation. The radioactive source was Cs-137, and the simulation was performed while moving in a semicircular shape with 15 degree steps from 0 degree to 180 degrees at a distance of 20 cm from the center point of the main sensor. Since the MCNP result indicates the probability of generating a pulse for one photon, this value was calculated based on 88.6 μCi to obtain an actual count. Through the ratio of the count values of the two sensors, it was determined whether the radioactive source was located in the front, side, or back of the probe.

Metals such as stainless steel and alloy 600 are used as structures and materials in nuclear power plants due to their excellent mechanical properties and heat resistance. And recently thermal and mechanical cutting technologies are being actively researched and developed for dismantling NPP. Among them, the mechanical cutting method has the advantage of less secondary waste generation such as fume and fine dust, but according to the wider the cutting range, the reaction force and the cutting device size are increased. In this paper, plasma assisted milling has been proposed to reduce the reaction force and device size, and the plasma efficiency was measured for SUS 316L. The plasma torch was operated at the level of 3 to 4 kW so that it was heated only without cutting. And the feedrate was set at 150 to 250 mm/min. The test confirmed that the plasma efficiency was 35% about SUS 316L, and it is expected that the numerical analysis using these test results can be used as basic data for plasma assisted milling.

Decommissioning plan of nuclear facilities require the radiological characterizations and the establishment of a decommissioning process that can ensure the safety and efficiency of the decommissioning workers. By utilizing the rapidly developed ICT technology, we have developed a technology that can acquire, analyze, and deliver information from the decommissioning work area to ensure the safety of decommissioning workers, optimize the decommissioning process, and actively respond to various decommissioning situations. The established a surveillance system that monitors nuclide inventory and radiation dose distribution at dismantling work area in real time and wireless transmits data for evaluation. Developed an evaluation program based on an evaluation model for optimizing the dismantling process by linking real-time measurement information. We developed a technology that can detect the location of dismantling workers in real time using stereovision cameras and artificial intelligence technology. The developed technology can be used for safety evaluation of dismantling workers and process optimization evaluation by linking the radionuclides inventory and dose distribution in dismantling work space of decommissioning nuclear power plant in the future.

Level measurement of liquid radwaste is essential for inventory management of treatment system. Among various methods, level measurement based on differential pressure has many advantages. First, it is possible to measure the liquid level of the system regardless of liquid type. Second, as the instrument doesn’t need to be installed near the tank, there is no need to contact the tank when managing it. Therefore, workers’ radiation dose from the system can be decreased. Finally, although it depends on the accuracy, the price of the instrument is relatively low. With these advantages, in general, liquid radwaste level in a tank is measured using differential pressure in the treatment system. Not only the advantages described above, there are some disadvantages. As the liquid in the system is waste, it is not pure but has some suspended materials. These materials can be accumulated in tanks and pipes where the liquids move to come into direct contact with pneumatic pipes that are essential in differential pressure instruments. As a result, in case of a treatment using heat source, the accumulated materials may become sludge causing interference in pneumatic pipes. And this can change the pressure which also affects the level measured. In conclusion, in case of liquid storage tanks in which the situation cannot be checked, the proficiency of an operator becomes important.

The burnup of spent fuel is one of the important management items that must be managed before storing the fuel in dry storage facilities, as well as for transportation and disposal in the future. Currently, the burnup of spent fuel is managed by calculating the design burnup at the time of design and measuring the real burnup using in-reactor measurement devices. Furthermore, to ensure the reliability of such data, the burnup of spent fuel can be measured using burnup measurement equipment to compare and analyze the data. In fact, KHNP is measuring the burnup of spent fuel using the burnup measurement equipment (SICOM-NG-FA) developed by ENUSA in Spain. The burnup measurement equipment analyzes the axial burnup profile of spent fuel using gamma and neutron detectors. Burnup measurement is performed by moving the spent fuel up and down inside the measurement equipment and measuring the burnup of the fuel surface facing the gamma and neutron detectors. This paper aims to compare the results of measuring the burnup of spent fuel on two sides versus four sides using the burnup measurement equipment.

Background: In general, measurement qualities of cross-culturally adapted quality of life (QOL) measures are altered in many aspects, although versions of them are well-validated measures. The latent trait and measurement qualities of the QOL measures for cancer-related samples should be considered when developing cross-culturally adapted measures. Objects: To investigate the latent trait of the translated into Korean World Health Organization Quality of Life-BREF (WHOQOL-BREF) administered to different cancer survivors who had palliative rehabilitation care service (PRCS). Methods: A cross-sectional study with 139 cancer survivors who had an experience of cancer survivorship with PRCS were conducted with a two-step analytic procedure including exploratory factor analysis (EFA) to confirm the latent trait and Rasch rating scale modeling to investigate the measurement qualities of the cross-culturally adapted WHOQOL-BREF measure. Results: While the original WHOQOL-BREF measure constitutes a 4-latent trait, the EFA reveals that 24 items constitute six substantial factors. The item loadings are predominantly spread over factors 1 through 4 in a mixed manner of the latent traits, while the loadings of ‘physical health’ and ‘environmental health’ latent traits show similarity to what the original measure intended to assess. The latent trait of the cross-culturally adapted WHOQOL-BREF measure administered to different cancer survivors is likely to reveal more dimensions than the original WHOQOL-BREF measure. Person reliability (i.e., analogous to Cronbach’s alpha) and separation are measured with 0.92 and 3.48, respectively. All items except the one item (medical treatment item) fit the Rasch rating model. Conclusion: Findings suggest that the latent trait and the measurement qualities of the cross-culturally adapted WHOQOL-BREF measure should be taken into consideration when applying versions of it to various populations.

Background: While efforts have been made to differentiate fall risk in older adults using wearable devices and clinical methodologies, technologies are still infancy. We applied a decision tree (DT) algorithm using inertial measurement unit (IMU) sensor data and clinical measurements to generate high performance classification models of fall risk of older adults. Objects: This study aims to develop a classification model of fall risk using IMU data and clinical measurements in older adults. Methods: Twenty-six older adults were assessed and categorized into high and low fall risk groups. IMU sensor data were obtained while walking from each group, and features were extracted to be used for a DT algorithm with the Gini index (DT1) and the Entropy index (DT2), which generated classification models to differentiate high and low fall risk groups. Model’s performance was compared and presented with accuracy, sensitivity, and specificity. Results: Accuracy, sensitivity and specificity were 77.8%, 80.0%, and 66.7%, respectively, for DT1; and 72.2%, 91.7%, and 33.3%, respectively, for DT2. Conclusion: Our results suggest that the fall risk classification using IMU sensor data obtained during gait has potentials to be developed for practical use. Different machine learning techniques involving larger data set should be warranted for future research and development.

This paper reports the results of an experimental examination using X-rays to test annealing materials for lapped bearing steel (STB2), to confirm the validity of the weighted averaging analysis method. The distribution behavior for the sin diagram and the presence or absence of differences in the peak method, half-value breadth method, and centroid method were investigated. When lapping the annealed bearing steel (STB2) material, a residual stress state with a non-directional steep gradient appeared in the surface layer, and it was found that the weighted averaging analysis method was effective. If there is a steep stress gradient, the sin diagram is curved and the diffraction intensity distribution curve becomes asymmetric, resulting in a difference between the peak method, half-value breadth method, and centroid method. This phenomenon was evident when the stress gradient was more than 2~3 kg/mm2/μm. In this case, if the position of the diffraction line is determined using the centroid method and the weighted averaging analysis method is applied, the stress value on the surface and the stress gradient under the surface can be obtained more accurately. When the stress gradient becomes a problem, since the curvature of the sin diagram appears clearly in the region of sin > 0.5, it is necessary to increase the inclination angle  as much as possible. In the case of a lapping layer, a more accurate value can be obtained by considering  in the weighted averaging analysis method. In an isotropic biaxial residual stress state, the presence or absence of  can be determined as the presence or absence of strain for sin≈0.4.