• Structural Engineering and Mechanics
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• 제10권3호
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• pp.263-275
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• 2000

In this paper, a core wall structure coupled with connecting beams is discretized and modeled as an equivalent thin-walled member with closed section, while the connecting beams between openings are replaced by an equivalent shear diaphragm. Then, a numerical method (finite member element method, FMEM) for dynamic analysis of the core wall structure is proposed. The numerical method combines the advantages of the FMEM and Vlasov's thin-walled beam theory and the effects of torsion, warping and, especially, the shearing strains in the middle surface of the walls are considered. The results presented in this paper are very promising compared with the ones obtained from finite element method.

• 한국소음진동공학회논문집
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• 제17권9호
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• pp.819-825
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• 2007

Vibration characteristics of an duel-cooling cylindrical fuel rod, which was proposed as a candidate design of fuel's cross section for the ultra-high burnup nuclear fuel, according to the cross-sectional dimensions and the number of supports or the span length were analytically studied. Finite element(FE) modeling for the annular cross sectional fuel was based on the methodology, that have been proven by the test verification, for the conventional PWR nuclear fuel rod. A commercial FEA code, ABAQUS, was used for the FE modeling and analysis. A planar beam element (B21) that uses a linear interpolation was used for the fuel rod and a linear spring element for the spring and dimple of the SG. Natural frequencies and mode shape were calculated according to the preliminary design candidates for the fuel's cross sectional dimension and the number of span. From the analysis results, the design scheme of the annular fuel compatible to the present PWR nuclear reactor core was discussed in terms of the number of supports and fuel's cross section.

• 대한토목학회논문집
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• 제5권1호
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• pp.55-64
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• 1985

본(本) 논문(論文)은 필댐에 있어서 최적심벽(最適心壁) 설계(設計)의 기준(基準)이 될 수 있도록 21개(個)의 심벽모형별(心壁模型別) 침투류(浸透流) 해석(解析)에 대한 실험(實驗)을 실시(實施)하여 경사면(傾斜面)의 기울기 변화(變化)로 침투류량(浸透流量)의 증감율(增減率)에 대해서 규명하였고, 특히 경사심벽(傾斜心壁)에서의 적정(適定) 설계경사(設計傾斜)를 찾아 보았다. 그리고 현재(現在)까지 발표(發表)된 근사이론식(近似理論式)에 실험치(實驗値)를 대입(代入)하여 이론침투류량(理論浸透流量)을 구(求)하고 실험치(實驗値)와 비교연구(比較硏究)하였으며, 검토결과(檢討結果) 실험치(實驗値)에 가장 가까운 이론공식(理論公式)도 찾았다. 또한 상류(上流)로 기울어진 경사심벽(傾斜心壁)에서의 침윤선형(浸潤線形)과 유출점(流出點)에 대해서도 고찰(考察)하고 현재(現在)까지 발표(發表)된 이론식(理論式)의 적합유무(適合有無)도 검토(檢討)하였다. 이상(以上)을 연구(硏究)하여 필댐의 심벽설계시(心壁設計時) 최적단면결정(最適斷面決定)을 위한 보다많은 자료(資料)를 제시(提示)하고자 하였다.

• 지질공학
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• 제26권2호
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• pp.277-290
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• 2016

심부지질조사에는 많은 경비와 시간이 필요해 심부지질을 해석하는데 많은 어려움이 있다. 그러나 지열모델링과 같이 많은 경비를 투자할 수는 없지만 심부의 지질정보가 필요한 경우 제한적이지만 천부의 지질정보를 이용하여 심부의 지질을 해석하고 추정할 수 있다. 이번 연구에서는 이러한 제한된 심부자료를 가진 지역에서 천부지질자료를 활용하여 어떻게 심부의 지질에 대한 정보를 추정할 수 있는지를 보여주고자 하였다. 이번 연구의 목적은 한반도 남동부를 관통하는 양산단층이 이 지역의 지열분포에 어떠한 영향을 주고 있는지를 연구하기 위하여 심부지질단면도를 획득하기 위한 것이다. 따라서 양산단층과 주변 단층들의 특징을 가장 잘 반영할 것으로 판단되는 울주군 상북면과 웅촌면 지역에서 양산단층을 가로지르는 NW-SE 방향으로 단면을 설정하였다. 이 심부 지질단면을 작성하기 위하여 먼저 기존 지질도를 검토하여 발달하는 암상의 분포와 주요 지질구조를 확인하였으며, 야외조사자료를 기반으로 도학적인 분석을 실시하여 지층의 심부연장성을 추정하였고, 지표에서 노출된 단층 등의 발달규모 및 자세를 통해 심부로의 연장가능성을 추정하였다. 또한 비록 천부자료이긴 하지만 기존 물리검층자료와 시추자료를 종합하여 한반도 남동부 양산단층대의 심부단면도를 작성하였다. 양산단층 주변의 암상에 대한 야외지질조사 결과 양산단층의 서쪽지괴에는 화강암이 주를 이루며, 양산단층의 동쪽지괴는 퇴적암류와 이를 관입한 화성암류가 주로 발달하고 있다. 지표상 드러난 양산단층의 연장성을 통해 규모를 추정해 볼 때 지하로 수 km 이상 발달할 것으로 추정되며, 물리검층자료를 분석한 결과 양산단층과 인접한 퇴적암류는 그 깊이가 얇고, 동쪽으로 갈수록 두꺼워지는 양상을 보인다. 이러한 자료를 종합 해석하여 모식적인 지질단면을 제작하였다. 비록 지질학적 개념에 기초하여 가능한 정보를 수집하였지만 이러한 천부자료에 기초한 심부단면도의 작성은 신뢰성이 매우 제한적이라는 것을 고려하는 것이 필요하다. 또한 이번 연구에서는 시추코어의 단열분석을 통해 단층의 존재를 인식할 수 있는 새로운 방법을 제시하였다. 이는 앞으로 시추자료 분석을 통해 단층의 존재와 규모를 판단하는데 매우 유용하게 활용될 수 있을 것으로 판단된다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2004년도 추계학술발표회 발표논문집
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• pp.143-144
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• 2004

• 대한전기학회논문지:전력기술부문A
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• 제48권2호
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• pp.119-126
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• 1999

Current transformer (CT) saturation may cause a variety of protective relays to malfunction. The conventional CT is designed that it can carry up to 20 times the rated current without exceeding 10% ratio error. However, the possibility of CT saturation still remains if the fault current contains substantial amounts of ac and/or dc components. This paper presents a design method of iron-cored CTs for use with protective relays to prevent CT saturation. The proposed design method determines the core cross section of the CT; it employs the transient dimensioning factor to consider relay's operating time (duty cycle) and dc component as well as ac components contained in the fault current, and symmetrical short-circuit current factor to consider as well as ac components contained in the fault current, and symmetrical short-circuit current factor to consider the biggest fault current. The method designs the cross section of CTs in cases of reclosure and no reclosure.

• Steel and Composite Structures
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• 제38권2호
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• pp.121-139
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• 2021

Ultra-high strength concrete (UHSC) encased steel columns are receiving growing interest in high-rise buildings owing to their economic and architectural advantages. However, UHSC encased steel columns are not covered by the modern fire safety design code. A total of 14 fire tests are conducted on UHSC (120 MPa) encased steel columns under constant axial loads and exposed to ISO-834 standard fire. The effect of load ratio, slenderness, stirrup spacing, cross-section size and concrete cover to core steel on the fire resistance and failure mode of the specimens are investigated. The applicability of the tabulated method in EC4 (EN 1994-1-2-2005) and regression formula in Chinese code (DBJ/T 15-81-2011) to fire resistance of UHSC encased steel columns are checked. Generally, the test results reveal that the vertical displacement-heating time curves can be divided into two phases, i.e. thermal expansion and shortening to failure. It is found that the fire resistance of column specimens increases with the increase of the cross-section size and concrete cover to core steel, but decreases with the increase of the load ratio and slenderness. The EC4 method overestimates the fire resistance up to 186% (220 min), while the Chinese code underestimates it down to 49%. The Chinese code has a better agreement than EC4 with the test results since the former considers the effect of the load ratio, slenderness, cross section size directly in its empirical formula. To estimate the fire resistance precisely can improve the economy of structural fire design of ultra-high strength concrete encased steel columns.

• Nuclear Engineering and Technology
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• 제52권3호
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• pp.461-468
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• 2020

The improvements of the DeCART/MUSAD code system for uncertainty analysis of HTGR neutronic parameters are presented in this paper. The function for quantifying an uncertainty of critical-spectrumweighted few group cross section was implemented using the generalized adjoint B₁ equation solver. Though the changes between the infinite and critical spectra cause a considerable difference in the contribution by the graphite scattering cross section, it does not significantly affect the total uncertainty. To reduce the number of iterations of the generalized adjoint transport equation solver, the generalized adjoint B₁ solution was used as the initial value for it and the number of iterations decreased to 50%. To reflect the implicit uncertainty, the correction factor was derived with the resonance integral. Moreover, an additional correction factor for the double heterogeneity was derived with the effective cross section of the DH region and it reduces the difference from the complete uncertainty. The code system was examined with the MHTGR-350 Ex.II-2 3D core benchmark. The k_eff uncertainty for Ex.II-2a with only the fresh fuel block was similar to that of the block and the uncertainty for Ex.II-2b with the fresh fuel and the burnt fuel blocks was smaller than that of the fresh fuel block.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1996년도 춘계학술발표회논문집(2)
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• pp.467-472
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• 1996

This study discusses special aspects of severe accident related recriticality modeling and analysis in the Advanced Neutron Source (ANS) reactor.$^{1, 2)}$ The analytical comparison of three elements core to former two elements case is conducted including evaluation of suitable nuclear cross-section sets to account for the effects of system configulation, fuel and moderator mixture temperature, material dispersion and the other thermal-hydraulics. Three elements core ANS reactor is the alternative core design which was proposed as a modified core design, with three fuel elements instead of two, that would allow operation with only 50% enriched uranium (former uranium fuel is the baseline design value of 93%) A comprehensive test matrix of calculations to evaluate the threat of a criticality event in the ANS is described. Strong dependencies still on geometry, material constituents, and thermal-hydraulic conditions are verified. Therefore, the concepts of mitigative design features are qualified.d.

• Steel and Composite Structures
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• 제34권1호
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• pp.53-73
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• 2020

A novel all-steel miniature bar-type structural fuse (MBSF) with cold formed bolted connections is developed in this study, which consists of a central energy dissipation core cut from a smooth round bar, an external confining tube and nuts. Three types of cross sections for the central energy dissipation core, i.e., triple-cut, double-cut and single-cut cross sections, were studied. Totally 18 specimens were axially tested under either symmetric or asymmetric cyclic loading histories, where the parameters such as cut cross sectional area ratio, length of the yielding portion and cross sectional type were investigated. Numerical simulation of 2 representative specimens were also conducted. An analytical model to evaluate the bending failure at the elastic portion was proposed, and a design method to avoid this failure mode was also presented. The experimental results show that the proposed MBSFs exhibit satisfactory hysteretic performance under both the two cyclic loading histories. Average strain values of 8% and 4% are found to be respectively suitable for designing the new MBSFs as the ultimate strain under the symmetric and asymmetric cyclic loadings.