• 한국전기전자재료학회논문지
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• 제19권3호
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• pp.301-306
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• 2006

The electron drift velocity W and the product of the longitudinal diffusion coefficient and the gas number density $ND_{L}$ in the $0.525\;\%$ and $5.05\;\%$ $C_{3}F_8-Ar$ mixtures were measured by using the double shutter drift tube with variable drift distance over the E/N range from 0.03 to 100 Td and gas pressure range from 1 to 915 torr. And we determined the electron collision cross sections set for the $C_{3}F_8$ molecule by STEP 1 of electron swarm method using a multi-term Boltzmann equation analysis. Our special attention in the present study was focused upon the vibrational excitation and new excitations cross sections of the $C_{3}F_8$ molecule.

• Computers and Concrete
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• 제11권6호
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• pp.515-529
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• 2013

The moment-curvature relation for simple bending is a well-studied subject and the classical moment-curvature diagram is commonly found in literature. The influence of axial forces has generally been considered as compression onto symmetrically reinforced cross-sections, thus strain at the reference fiber never has been an issue. However, when dealing with integral structures, which are usually statically indeterminate in different degrees, these concepts are not sufficient. Their horizontal elements are often completely restrained, which, under imposed deformations, leads to moderate compressive or tensile axial forces. The authors propose to analyze conventional beam cross-sections with moment-curvature diagrams considering asymmetrically reinforced cross-sections under combined influence of bending and moderate axial force. In addition a new diagram is introduced that expands the common moment-curvature relation onto the strain variation at the reference fiber. A parametric study presented in this article reveals the significant influence of selected cross-section parameters.

• Composites Research
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• 제17권4호
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• pp.25-31
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• 2004

본 연구에서는 다중세포로 구성된 타원형 단면 복합재료 블레이드의 정밀 1차원 보 해석모델을 개발하였다. 보의 정식화를 위하여 Reissner의 반보족에너지 함수를 이용하였으며, 고전적인 강성도 및 유연도법을 결합한 혼합보 이론 체계를 구축하였다. 타원단면의 특성계수들을 구하기 위해 단면의 외곽선을 유한개의 선분으로 분할하고 여기에 Gauss 적분을 수행하였다. 또한, 단면을 구성하는 각 세포에 대해 4개의 연속방정식이 충족되도록 구성하였다. 개발된 보 이론을 단일 및 이중세포로 구성된 타원형 복합재료 블레이드에 적용하였으며, 다차원 정밀 유한요소 해석 결과와 비교하여 그 타당성을 확보하였다.

• Nuclear Engineering and Technology
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• 제17권2호
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• pp.98-104
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• 1985

가압중수로인 CANDU의 노심에는 많은 반응도 조절장치들이 분포되어 있어 출력분포와 잉여반응도를 조절하며, 이러한 장치들의 효자는 노심해서에서 증분격자상수로 나타낸다. 격자코드인 WIMS를 사용하여 2군 군정수를 계산하고 이를 이용하여 SUPERCELL코드로 증분 격자상수를 생산하였다. 증분격자상수는 조정봉과 지역조절장치에 대해 노심해석을 통해 평가하였으며 반응도가와 채널출력을 참고 자료와 비교하였다. 반응도가와 최대채널출력 오차가 참고값에 대해 각각 0.97%와 0.6% 범위 내에서 나타났다.

• 지구물리와물리탐사
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• 제5권2호
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• pp.93-98
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• 2002

"이산적으로 정의된 수평단면으로부터 광체의 3차원 형태를 생성하는 3D Modeler"시스템을 사용하여 국내의 한 광산에서 개발중인 실제 광체의 모델링을 수행하였다. 이 프로그램을 사용하면 다양한 공간정보를 쉽게 종합하여 모델링을 할 수 있다. 모델링의 결과는 인접한 단면사이를 연결하는 제어점들의 설정에 크게 좌우된다. 제어점의 설정은 단면간의 기하학적 유사성과 광체의 지질학적인 특성 등을 고려하여 작성한다. 작성된 모델은 광체를 3차원적으로 도시하거나 또는 임의의 단면을 추출하여 검토할 수 있으며 이 단면을 수정하여 다시 모델링함으로써 점진적으로 사용자가 원하는 형태의 모델을 구축할 수 있다.

• Computers and Concrete
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• 제19권3호
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• pp.233-241
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• 2017

During the last two decades, CFRP have been extensively used for repair and rehabilitation of existing structures as well as in new construction applications. For rehabilitation purposes CFRP are currently used to increase the load and the energy absorption capacities and also the shear strength of concrete columns. Thus, the effect of CFRP confinement on the strength and deformation capacity of concrete columns has been extensively studied. However, the majority of such studies consider empirical relationships based on correlation analysis due to the fact that until today there is no general law describing such a hugely complex phenomenon. Moreover, these studies have been focused on the performance of circular cross section columns and the data available for square or rectangular cross sections are still scarce. Therefore, the existing relationships may not be sufficiently accurate to provide satisfactory results. That is why intelligent models with the ability to learn from examples can and must be tested, trying to evaluate their accuracy for composite compressive strength prediction. In this study the forecasting of wrapped CFRP confined concrete strength was carried out using different Data Mining techniques to predict CFRP confined concrete compressive strength taking into account the specimens' cross section: circular or rectangular. Based on the results obtained, CFRP confined concrete compressive strength can be accurately predicted for circular cross sections using SVM with five and six input parameters without spending too much time. The results for rectangular sections were not as good as those obtained for circular sections. It seems that the prediction can only be obtained with reasonable accuracy for certain values of the lateral confinement coefficient due to less efficiency of lateral confinement for rectangular cross sections.

• Nuclear Engineering and Technology
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• 제54권3호
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• pp.959-964
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• 2022

Lead is an important material, both for fusion or fission reactors. The cross sections of natural lead should be validated because lead is a main component of lithium-lead modules suggested for fusion power plants and it directly affects the crucial variable, tritium breeding ratio. The presented study discusses a validation of the lead transport libraries by dint of the activation of carefully selected activation samples. The high emission standard ²⁵²Cf neutron source was used as a neutron source for the presented validation experiment. In the irradiation setup, the samples were placed behind 5 and 10 cm of the lead material. Samples were measured using a gamma spectrometry to infer the reaction rate and compared with MCNP6 calculations using ENDF/B-VIII.0 lead cross sections. The experiment used validated IRDFF-II dosimetric reactions to validate lead cross sections, namely ¹⁹⁷Au(n, 2n)¹⁹⁶Au, ⁵⁸Ni(n,p)⁵⁸Co, ⁹³Nb(n, 2n)^92mNb, ¹¹⁵In(n,n')^115mIn, ¹¹⁵In(n,γ)^116mIn, ¹⁹⁷Au(n,γ)¹⁹⁸Au and ⁶³Cu(n,γ)⁶⁴Cu reactions. The threshold reactions agree reasonably with calculations; however, the experimental data suggests a higher thermal neutron flux behind lead bricks. The paper also suggests ²⁵²Cf isotropic source as a valuable tool for validation of some cross-sections important for fusion applications, i.e. reactions on structural materials, e.g. Cu, Pb, etc.

• Nuclear Engineering and Technology
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• 제45권6호
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• pp.753-758
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• 2013

A new method of calculating sensitivity coefficients of core characteristics relative to infinite-dilution cross sections has been developed. Conventional sensitivity coefficients are evaluated for the changes of effective cross sections which are dependent on individual models of core and cell. Therefore a correction has been derived to the conventional sensitivity coefficients based on the perturbation theory. The accuracy of the present method has been verified by comparing numerical results of sensitivity coefficients with a reference Monte-Carlo method.

• 한국지리정보학회지
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• 제12권4호
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• pp.95-112
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• 2009

하천의 흐름해석 분야에서 모형이 요구하는 입력자료 중 하천단면은 매우 중요한 요소이다. 수치모형을 이용해서 자연하천의 2차원 흐름을 모의하고자 할 때 정확한 계산치를 얻기 위해서는 실제 하천단면의 하상을 정확하게 반영하여야 한다. 그러나 하천단면의 하상을 실제 상태의 모습 그대로 반영하는 것은 거의 불가능하다. 본 연구에서는 현재 실무에서 사용하는 하천측량 자료인 HEC단면과 ArcView를 연계하여 등간격 하도단면을 생성하고 유한요소망을 구축하는 방법을 제안하였다. 연구 대상지역은 한강 본류 구간과 낙동강 본류 구간을 선정하였고 등간격 하도단면 구축결과 실측 단면자료와 잘 일치함을 확인할 수 있었다. 또한 본 연구에서 제안한 등간격 하도단면을 이용하면 2차원 흐름해석 및 수질해석을 위한 양질의 유한요소망을 구축하여 유한요소해석 등에 유용하게 사용될 수 있을 것이다.

• Nuclear Engineering and Technology
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• 제56권4호
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• pp.1204-1212
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• 2024

To accurately calculate the heating distribution of the fast reactor, a neutron-photon library in MATXS format named Knight-B7.1-1968n × 94γ was processed based on the ENDF/B-VII.1 library for ultrafine groups. The neutron cross-section processing code MGGC2.0 was used to generate few-group neutron cross sections in ISOTXS format. Additionally, the self-developed photon cross-section processing code NGAMMA was utilized to generate photon libraries for neutron-photon coupled heating calculations, including photo-atom cross sections for the ISOTXS format, prompt photon production cross sections, and kinetic energy release in materials (KERMA) factors for neutrons and photons, and the self-shielding effect from the capture and fission cross sections of neutron to photon have been taken into account when the photon source generated by neutron is calculated. The interface code GSORCAL was developed to generate the photon source distribution and interface with the DIF3D code to calculate the neutron-photon coupling heating distribution of the fast reactor core. The neutron-photon coupled heating calculation route was verified using the ZPPR-9 benchmark and the RBEC-M benchmark, and the results of the coupled heating calculations were analyzed in comparison with those obtained from the Monte Carlo code MCNP. The calculations show that the library was accurately processed, and the results of the fast reactor neutron-photon coupled heating calculations agree well with those obtained from MCNP.