• 한국공작기계학회논문집
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• 제17권4호
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• pp.112-118
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• 2008

In order to meet the optical performance in the process of the micro lens manufacturing with plastics, it is important to embody accuracy in shape and surface roughness to the intended design. Since it is difficult to machine exactly the mold core of lens fit to the designed shape, in this paper, a simple program using MATLAB is developed for shape correction of the mold core after first machining it. This program evaluates correction parameters(aspheric coefficients and curvature) and generates aspheric NC data for compensating the core surface in prior machining process. The program provides the way to manufacture plastic injection molding lens with aspheric shape of high precision, and is expected to be effective for correction and to shorten the processing time.

• 한국콘크리트학회:학술대회논문집
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• 한국콘크리트학회 2002년도 봄 학술발표회 논문집
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• pp.973-978
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• 2002

This study was performed to verify the effect of various testing conditions affecting measured compressive strength of concrete core and to compute the correction coefficients for it. Conditions of specimens affecting test results include size(diameter), height-diameter ratio, humidity of specimen, amount and arrangement of bar, core direction from structure and method of end preparation. In testing core strength of concrete, special cares should be taken on various testing conditions whose effects have been latent in conventional concrete.

• 지질공학
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• 제9권3호
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• pp.253-265
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• 1999

충청북도 제천 지역에 있는 갑산층 퇴적암을 대상으로 지구물리검층과 실내 코어물성 측정에 의한 물성 반응 특성을 연구하였다. 자연감마와 전기비저항 및 밀도를 대상으로 하여 지구물리검층과 실내 코어물성 사이에 나타나는 유사성과 차이점을 비교하는데 초점이 모아졌으며 특히 물리검층과 실내 코어물성 사이에 나타나는 차이점 분석 과정을 통하여 검층밀도 결정에 있어서 자연감마의 영향을 분석하였다. 자연감마의 영향 보정에 의하여 두 물성간의 상관성이 개선되고 검층해석 결과에서 신뢰도가 크게 향상되었다. 물성 값중에서는 갑산층 셰일의 밀도가 주변의 치밀질 석회암보다도 높게 나타나고 있음이 주목되었다.

• 한국방사선학회논문지
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• 제14권5호
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• pp.503-510
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• 2020

콘크리트는 원자력 시설의 차폐용 구조물로 광범위하게 사용되고 있는 재료이다. 하지만, 시설의 해체 시 양적으로 가장 많이 발생하는 방사성 폐기물이기도하다. 콘크리트는 중성자를 포획하여 다양한 방사성 핵종을 생성하기 때문에 해체 전에 시료를 채취하여 방사능 측정 및 평가를 수행해야 한다. 측정은 주로 HPGe 검출기를 이용하는데 시료의 정확한 방사능 판정을 위해는 기하학적 보정인자, 자가흡수 보정인자, 계측기의 절대효율 등 효과적인 보정인자를 측정치에 반영해야 한다. 보정인자는 기하학적 및 화학적 상태가 실제 시료와 동일한 표준시료를 이용해서 동일한 측정조건 하에서 획득한다. 하지만, 콘크리트는 다양한 구성물질과 높은 밀도로 전처리가 제한적이므로 콘크리트 표준시료를 제작하는 것은 매우 어렵다. 또한 코어드릴(core drill)을 사용하여 채취되는 콘크리트 시료는 체적선원이므로 직경에 대한 기하학적 보정과 밀도에 대한 자가흡수에 대한 보정이 필수적이다. 따라서, 최근에는 많은 연구자들이 표준선원을 제작 후 측정하는 대신 몬테카를로 전산모사(Monte Carlo simulation)을 이용하여 효과적인 보정인자들을 계산하는 연구를 수행하고 있다. 본 연구에서는 Monte Carlo code 중 하나인 Geant4를 이용하여 방사화 콘크리트에서 가장 많이 생성되는 핵종인 ¹⁵²Eu, ⁶⁰Co에서 방출되는 감마선 에너지에 대한 콘크리트 코어시료의 직경과 밀도에 따른 보정인자를 산출하였다.

• Nuclear Engineering and Technology
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• 제34권1호
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• pp.68-79
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• 2002

The approach for evaluating the critical heat flux (CHF) margin using the departure from nucleate boiling ratio (DNBR) concept has been widely applied to PWR core design, while DNBR in this approach does not indicate appropriately the CHF margin in terms of the attainable power margin-to-CHF against a reactor core condition. The CHF power margin must be calculated by increasing power until the minimum DNBR reaches a DNBR limit. The Critical Power Ratio (CPR), defined as the ratio of the predicted CHF power to the operating power, is considered more reasonable for indicating the CHF margin and can be calculated by a CPR orrelation based on the heat balance of a test bundle. This approach yields directly the CHF power margin, but the calculated CPR must be corrected to compensate for many local effects of the actual core, which are not considered in the CHF test and analysis. In this paper, correction of the calculated CPR is made so that it may become equal to the DNB overpower margin. Exemplary calculations showed that the correction tends to be increased as power distribution is more distorted, but are not unduly large.

• Nuclear Engineering and Technology
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• 제55권3호
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• pp.1084-1096
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• 2023

On-the-fly(OTF) generation of Spectral Superhomogenization(SSPH) factors is analyzed in the multigroup(MG) whole core calculation employing pin-wise continuous energy(CE) slowing-down solutions. The motivation for the work is to avoid the huge computing time required for the generation of a parametrized SSPH factor library(PSSL) which is used to resolve the angular dependency of MG resonance cross sections, and also to exploit the advantage of flexible choice of a MG structure by using CE slowing-down solutions. Two pin-wise CE slowing-down methods, the equivalent Dancoff cell method and the shadowing effect correction method, are evaluated with the OTF SSPH method. The effectiveness of the OTF SSPH method is examined for various simplified and realistic core problems with various MG structures. It is demonstrated that the computing time overhead of this method is negligible whereas the solution accuracy is considerably enhanced.

• 한국운동역학회지
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• 제28권2호
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• pp.119-125
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• 2018

Objective: The purpose of this study was to compare the effect of different 12-week exercise programs for posture correction on postural alignment in elderly women. Method: The study included 36 elderly women who were randomly divided into 3 groups: Group A (core exercise, n=12), Group B (combined exercise, n=12), and Group C (Pilates exercise, n=12). Postural alignment was measured using 6 variables in frontal and sagittal planes. Two-way mixed analysis of variance was used to compare the effect of exercise program types on postural alignment and a paired t-test was used to compare differences in postural alignment after exercise. Results: The core exercise group showed statistically significant improvement (p<.05) in multiple upper and lower body postural alignment measurements. The combined exercise and Pilates exercise groups showed statistically significant improvement (p<.05) in upper body measurements alone. Conclusion: Core exercise, combined exercise, and Pilates exercise improved postural alignment in elderly woman through improvement in muscle strength and ligament flexibility around the spine and pelvis.

• 한국군사과학기술학회지
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• 제8권3호
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• pp.42-50
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• 2005

In this paper, a novel method is proposed how the ECC(Error Correction Code) in server system can be investigated and the robustness of each system against noisy environment and element failure in memory module has been verified. Chipset manufacturers have hided the algorithm of their Hamming code and the user has difficulty in verification of the robustness of each system. The proposed method is very simple, but the outputs of the experiment explain the core ability of error correction in server system and helps the detection of the failure element. On the basis of these results, we could expect the robustness of digitalized weapon system and the efficient design of our own error correction code.

• Nuclear Engineering and Technology
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• 제49권8호
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• pp.1600-1609
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• 2017

The accelerator-driven subcritical system (ADS) is driven by a neutron source from spallation reactions introduced by the injected proton beam. Part of the neutron source has energy as high as a few hundred MeV to a few GeV. The effects of high-energy source neutrons ($E_n$ > 20 MeV) are usually approximated by energy cut-off treatment in practical core calculations, which can overestimate the predicted proton beam current in the ADS design. This article intends to quantize this effect and propose a way to solve this problem. To evaluate the effects of high-energy neutrons in the subcritical core, two models are established aiming to cover the features of current experimental facilities and industrial-scale ADS in the future. The results show that high-energy neutrons with $E_n$ > 20 MeV are of small fraction (2.6%) in the neutron source, but their contribution to the source efficiency is about 23% for the large scale ADS. Based on this, a neutron source efficiency correction factor is proposed. Tests show that the new correction method works well in the ADS calculation. This method can effectively improve the accuracy of the prediction of the proton beam current.

• Nuclear Engineering and Technology
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• 제54권9호
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• pp.3488-3493
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• 2022

Accelerator driven subcritical systems have long been discussed as facilities which can be used for solving the nuclear waste problem. The physics of these systems is very different from conventional reactors and new techniques had to be developed for reactivity monitoring. One such technique is the Area Ratio Method which studies the response of a subcritical system upon insertion of a large number of neutron pulses. An issue associated with this technique is the spatial dependence of measured reactivity which is intrinsic to the sub criticality of the system since the reactor does not operate on the fundamental mode and measured reactivity depends on the detector position. This is generally addressed by defining Bell-Glasstone spatial correction factor. This factor upon multiplication with measured reactivity gives the correct reactivity which is independent of detector location. Monte Carlo Methods are used for evaluating these factors. This paper presents a complete three dimensional map of spatial correction factors for BRAHMMA subcritical system. In addition, the dataset obtained also helps in identifying detector locations where the correction factor is close to unity, thereby implying no correction if the detector is used at those locations.