• 한국전자통신학회논문지
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• 제16권2호
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• pp.293-300
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• 2021

본 연구에서는 SCDF를 사용하여 전력공급의 가치를 산정하고, 부하점별 중요도를 다면적인 평가를 하는 방법을 제시한다. 이의 방법으로 지속정전, 순간정전, 전압 Sag/Swell에 대응할 수 있는 SCDF를 제공하고, 이 SCDF를 사용하여 정전과 관련하여 어느 부하점에 어느 정도의 비용이 발생하는지를 계산하였으며, 이들 비용을 다면평가를 통해 어느 부분이 어느정도 취약한지를 평가하고 어느 부분의 확장이 필요한 지를 수치적으로 설명할 수 있도록 하였다. 본 연구를 우리나라의 실배전계통에 적용하여 평가하고 유용성을 검증하였다.

• Nuclear Engineering and Technology
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• 제53권1호
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• pp.44-60
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• 2021

In this paper, we validate the decay heat calculation capability via a two-step method to analyze spent nuclear fuel (SNF) discharged from pressurized water reactors (PWRs). The calculation method is implemented with a lattice code STREAM and a nodal diffusion code RAST-K. One of the features of this method is the direct consideration of three-dimensional (3D) core simulation conditions with the advantage of a short simulation time. Other features include the prediction of the isotope inventory by Lagrange non-linear interpolation and the use of power history correction factors. The validation is performed with 58 decay heat measurements of 48 fuel assemblies (FAs) discharged from five PWRs operated in Sweden and the United States. These realistic benchmarks cover the discharge burnup range up to 51 GWd/MTU, 23.2 years of cooling time, and spanning an initial uranium enrichment range of 2.100-4.005 wt percent. The SNF analysis capability of STREAM is also employed in the code-to-code comparison. Compared to the measurements, the validation results of the FA calculation with RAST-K are within ±4%, and the pin-wise results are within ±4.3%. This paper successfully demonstrates that the developed decay heat calculation method can perform SNF back-end cycle analyses.

• 한국산학기술학회논문지
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• 제17권12호
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• pp.686-691
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• 2016

용접강구조물에서는 용접비드와 같은 응력집중부가 많이 존재한다. 또한 용접부에서는 용접결함이 발생할 가능성이 많다. 반복적인 피로하중이 응력집중부에 작용하면 응력집중부에서 피로균열이 발생하고, 발생된 균열의 전파에 의해 피로파괴사고를 일으킨다. 따라서 피로파괴사고를 미연에 방지하기 위하여 균열발생수명과 균열전파수명과 같은 피로수명의 파악이 필요하다. 본 연구에서는 피로균열전파특성 연구에 사용되는 컴플라이언스를 도출하였다. 이 컴플라이언스는 피로균열의 자동화 측정에 활용할 수 있다. 본 연구에서는 CT시험편에 대하여 in-house FEM program을 사용하여 컴플라이언스를 계산하였다. 이 계산결과는 저자의 앞선 연구에서 본 프로그램을 사용하여 계산한 J integral의 계산결과와 대비하여 a/W와의 관계를 제시하였다. 그리고 또한 CT시험편 Back Face의 중앙부로부터 위아래 방향의 스트레인 분포에 계산을 실시하였다. 이 분포에서는 중심으로부터 위아래로 갈수록 스트레인이 감소하는 경향을 나타내었다. 이상의 계산과정으로부터 균열진전시험의 자동수행을 위한 컴플라이언스를 얻을 수 있었다. 이것으로부터 CT 시험편의 피로균열진전시험의 자동화에 활용이 가능하게 되었다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1999년도 추계학술발표회요약집
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• pp.355.2-355
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• 1999

The spnng back phenomena occurring in the coiling process of a steam generator tube induces the dimensional inaccuracy and makes the coiling procedure difficult. In this research, an analytical model was developed to evaluate the amount of the spring back for SMART steam generator tubes. The model was developed on the basis of beam theory and elastic-perfectly plastic material property. This model was extended to consider the effect of plastic hardening and the effect of the tensile force on the spring back phenomena. Parametric studies were performed for various design variables of steam generator tubes in order to minimize the spring back in the design stage. A sensitivity analysis has shown that the low yield strength, the high elastic modulus, the small helix diameter, and the large tube diameter result in a small amount of the spring back. The amount of the spring back can be controlled by the selection of adequate design values in the basic design stage and reduced to an allowable limit by the application of the tensile force to the tube during the coiling process.rocess.

• Nuclear Engineering and Technology
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• 제53권7호
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• pp.2104-2125
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• 2021

This paper presents the verification and validation (V&V) of a calculation module for isotope inventory prediction to control the back-end cycle of spent nuclear fuel (SNF). The calculation method presented herein was implemented in a two-step code system of a lattice code STREAM and a nodal diffusion code RAST-K. STREAM generates a cross section and provides the number density information using branch/history depletion branch calculations, whereas RAST-K supplies the power history and three history indices (boron concentration, moderator temperature, and fuel temperature). As its primary feature, this method can directly consider three-dimensional core simulation conditions using history indices of the operating conditions. Therefore, this method reduces the computation time by avoiding a recalculation of the fuel depletion. The module for isotope inventory calculates the number densities using the Lagrange interpolation method and power history correction factors, which are applied to correct the effects of the decay and fission products generated at different power levels. To assess the reliability of the developed code system for back-end cycle analysis, validation study was performed with 58 measured samples of pressurized water reactor (PWR) SNF, and code-to-code comparison was conducted with STREAM-SNF, HELIOS-1.6 and SCALE 5.1. The V&V results presented that the developed code system can provide reasonable results with comparable confidence intervals. As a result, this paper successfully demonstrates that the isotope inventory prediction code system can be used for spent nuclear fuel analysis.

• 한국의류산업학회지
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• 제18권1호
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• pp.91-102
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• 2016

This study classified the lower body types of female adults aged 18 to 69. The lower body was divided into front, lateral front, and lateral back. In order to understand the shape and somatotype of each segment, 592 people were analyzed based on girth, height, length, depth, width, angle and cross section distance for each segment. For data analysis, SPSS 18.0 was performed for descriptive statics, principal component analysis, K-means cluster analysis, ANOVA, and Duncan's test (as verification). Factor analysis was performed based on index values, calculation values, angles, and cross section distances. The measured items resulted in a.) 16 items were extracted to 5 factors in the case of the front factor (FF) of the lower body, and b.) 24 items were extracted to 6 factors in the case of lateral front factor (LFF) and lateral back factor (LBF). Each factor was put through K-means cluster analysis, classifying the lower bodies into one of four types of based on the front type (FT), the lateral front type (LFT), and the lateral back type (LBT) respectively. This study proposed an understanding of various lower body shapes by segmenting and classifying the lower body shapes for each type.

• Journal of electromagnetic engineering and science
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• 제10권3호
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• pp.166-170
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• 2010

To numerically calculate electromagnetic scattering from the electrical-large three-dimensional(3D) objects, the high-frequency approaches have been usually applied, but the accuracy and feasibility of these geometrical and physical optics(GO-PO) approaches, to some extent, are remained to be improved. In this paper, a new framework is developed for calculation of the near-field scattering field of an electrical-large 3D target by using a multilevel fast multipole algorithm(MLFMA) and generation of radar images by using a fast back-projection(FBP) algorithm. The MPI(Message Passing Interface) parallel computing is carried out to multiply the calculation efficiency greatly. Finally, a simple example of perfectly electrical conducting(PEC) patch and a canonical case of Fighting Falcon F-16 are presented.

• 의료ㆍ복지 건축 : 한국의료복지건축학회 논문집
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• 제14권2호
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• pp.3-14
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• 2008

The rehabilitation for the workplace accident victims is basically aimed to get them back to their working place through the secondary care processes which have some more special and more professional rehabilitation than any others, after the primary treatments like operation in an acute hospital since the accident. They need more concentrative rehabilitation efforts according to classified injury types during the period of acute, sub-acute and convalescent. This study is for the partial research of rehabilitation hospital for workers' accident victims and presents design data which can be used for the appropriate area calculation and spatial composition. Drawing documents analysis, interviews, observation were used to examine the condition of existing rehabilitation hospitals.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2001년도 하계학술대회 논문집 A
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• pp.452-454
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• 2001

This paper described the calculation results of lightning flashover rate on the 345kV and 154kV transmission system of KEPCO. The back-flashover rate and shielding failure rate was calculated by FLASH(lightning flashover rate calculation program from IEEE) and KEPRI's own program which is based on the EGM(Electro Geometrical Model) method. The estimated lightning flashover late of 345kV transmission system of double circuit was 1.0 flash per 100km-year, and the lightning flashover rate of 154kV transmission line was 2.0 flash Per 100km-year approximately.

• 전기의세계
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• 제29권1호
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• pp.65-72
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• 1980

Arstrong-Whitehead theory on effective shielding and shielding failure is extended so that it is applicable to vertical line configuration the existing approaches on back-flash rate calculation are summerized and compared in particular on Model Line, and the usefulness of the whitehead approach is suggested.