• Nuclear Engineering and Technology
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• 제49권4호
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• pp.838-849
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• 2017

This paper proposes penalty factor equations that take into consideration the weld strength over-match given in the classified form similar to the revised equations presented in the Code Case N-779 via cyclic elastic-plastic finite element analysis. It was found that the $K_e$ analysis data reflecting elastic follow-up can be consolidated by normalizing the primary-plus-secondary stress intensity ranges excluding the nonlinear thermal stress intensity component, $S_n$ to over-match degree of yield strength, $M_F$. For the effect of over-match on $K_n{\times}K_{\nu}$, dispersion of the $K_n{\times}K_{\nu}$ analysis data can be sharply reduced by dividing total stress intensity range, excluding local thermal stresses, $S_{p-lt}$ by $M_F$. Finally, the proposed equations were applied to the weld between the safe end and the piping of a pressurizer surge nozzle in pressurized water reactors in order to calculate a cumulative usage factor. The cumulative usage factor was then compared with those derived by the previous $K_e$ factor equations. The result shows that application of the proposed equations can significantly reduce conservatism of fatigue assessment using the previous $K_e$ factor equations.

• Nuclear Engineering and Technology
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• 제53권5호
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• pp.1652-1657
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• 2021

Nuclear materials can be utilized not only for peaceful uses, but also for military purposes; hence, the international community has devoted itself to the control, management and safeguarding of nuclear materials. Nuclear materials are of varying degrees of usability for development of nuclear weapons. Thus, several methods for assessing the attractiveness of nuclear materials for nuclear weapons purposes have been proposed. When these methods are applied to unirradiated depleted, natural, and low-enriched uranium (DU, NU, and LEU), they are certainly classified as non-attractive nuclear materials. However, when nuclear material attractiveness is to be evaluated for potential radiological dispersal device (RDD) uses, it is required to develop a different method for the different aspects and factors. In the present study, we derived a novel method for evaluating nuclear material attractiveness for use in RDD development. To this end, the specific activity and dose coefficient were identified as the two sub-factors, and, in consideration of those, the mass causing detrimental health effects was determined to be the main factor impacting on nuclear materials attractiveness. Based on this factor, the attractiveness of unirradiated DU, NU, and LEU for RDD use was qualitatively compared with that of ¹³⁷Cs.

• 대한토목학회논문집
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• 제26권6C호
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• pp.369-376
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• 2006

1차원 압밀시험에서 구해진 결과는 상사법칙을 적용하여 원지반의 침하량과 압밀시간을 추정하고 있다. 하지만 점토의 변형의존성, 층두께, 재하시간, 하중증분비 등에 의해 변화하기 때문에 상사법칙의 성립은 명확하게 밝혀지지 않고 있다. 본 연구는 재하시간과 층두께를 달리하여 압밀시험과 투수시험을 병행하여 상사법칙의 적용성을 나타내었다. 그 결과, f(=1+e)-logk관계는 점토의 특성을 잘 나타내고 있으며, $c_{\nu}$와 k는 보정이 필요없는 것으로 나타났으며, 상사법칙은 f-logp관계의 위치와 1차 압밀선에 의존하고 있다.

• 대한한방내과학회지
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• 제45권2호
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• pp.140-148
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• 2024

Objective: In this case study, we describe the use of Shihogayonggolmoryo-tang-gami to treat an in-patient with delirium. Methods: An in-patient with symptoms of delirium was treated with Korean medicine therapies, including the herbal medication Shihogagyonggolmoryo-tang-gami, for 7 days. To evaluate its therapeutic effect, we used the Nursing Delirium Screening Scale (Nu-DESC) and Memorial Delirium Assessment Scale (MDAS). Results: After the treatment, Nu-DESC and MDAS scores improved. Of note, instances of the patient calling out improved, in addition to the patient's sleeping pattern. Although all the symptoms of delirium did not disappear completely, Shihogayonggolmoryo-tang-gami had therapeutic effects. Conclusion: These results suggest that Shihogayonggolmoryo-tang-gami may have a beneficial effect on delirium, without using other antipsychotic medications.

• 대한방사성의약품학회지
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• 제3권2호
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• pp.65-71
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• 2017

To assess the effects of filter and reconstruction of Cu-64 PET data on Siemens scanner, the various reconstruction algorithm with various filters were assessed in terms of spatial resolution, non-uniformity (NU), recovery coefficient (RC), and spillover ratio (SOR). Image reconstruction was performed using filtered backprojection (FBP), 2D ordered subset expectation maximization (OSEM), 3D reprojection algorithm (3DRP), and maximum a posteriori algorithms (MAP). For the FBP reconstruction, ramp, butterworth, hamming, hanning, or parzen filters were used. Attenuation or scatter correction were performed to assess the effect of attenuation and scatter correction. Regarding spatial resolution, highest achievable volumetric resolution was $3.08mm^3$ at the center of FOV when MAP (${\beta}=0.1$) reconstruction method was used. SOR was below 4% for FBP when ramp, Hamming, Hanning, or Shepp-logan filter were used. The lowest NU (highest uniform) after attenuation & scatter correction was 5.39% when FBP (parzen filter) was used. Regarding RC, 0.9 < RC < 1.1 was obtained when OSEM (iteration: 10) was used when attenuation and scatter correction were applied. In this study, image quality of Cu-64 on Siemens Inveon PET was investigated. This data will helpful for the quantification of Cu-64 PET data.

• 대한기계학회논문집
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• 제11권1호
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• pp.1-18
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• 1987

본 연구에서는 입자가 부상된 이상난류제트유동에 Einstein의 확산모형, Pes- kin모형, 3-방정식 모형, 4-방정식 모형, 대수응력모형 등을 적용하여 해석하고 각 모 형들의 결과를 비교 분석하였다. 이상난류유동의 수치해석에서 공기는 제1유체유동 으로 하고 첨가되는 고체분말의 흐름은 밀도(.rho.$_{p}$), 층류동점성계수(.nu.$_{p}$), 과점성계수(.nu.$_{pt}$ )를 갖는 제2유체유동의 흐름으로 간주하였다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1997년도 춘계학술발표회논문집(1)
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• pp.484-488
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• 1997

Fission product release (FPR) assessment for 100% reactor outlet header (ROH) break in CANDU reactor loaded with CANFLEX-NU fuel bundles has been performed. The predicted results are compared with those for the reactor loaded with standard 37-element bundles. The fuel failure thresholds for the CANFLEX and standard bundle elements are very similar. All the sheaths at the corresponding fuel failure thresholds for the CANFLEX and standard bundles fail due to the significant cracks in the surface oxide, except those for the CANFLEX inner element at burnups of 220 to 240 MW.h/kg(U), which fail due to the excessive diametral strain. The fuel failure analysis predicts that the number of failed fuel elements for the CANFLEX bundle case is none, while that for the standard bundle case is 1827. The total (gap plus bound) I-131 releases for the CANFLEX and standard bundles are none and 5889 TBq, respectively The significant reduction of the number of failed fuel elements and FPR for the CABFKEX fuel bundle is attributed to the lower linear power of the CANFLEX fuel bundle compared with the standard fuel bundle.

• 한국전산유체공학회:학술대회논문집
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• 한국전산유체공학회 2008년도 학술대회
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• pp.111-117
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• 2008

This paper reports briefly on the computational results of a turbulent Rayleigh-Benard convection with the elliptic-blending second-moment closure (EBM). The primary emphasis of the study is placed on an investigation of accuracy and numerical stability of the elliptic-blending second-moment closure for the turbulent Rayleigh-Benard convection. The turbulent heat fluxes in this study are treated by the algebraic flux model with the temperature variance and molecular dissipation rate of turbulent heat flux. The model is applied to the prediction of the turbulent Rayleigh-Benard convection for Rayleigh numbers ranging from $Ra=2{\times}10^6$ to $Ra=10^9$, and the computed results are compared with the previous experimental correlations, T-RANS and LES results. The predicted cell-averaged Nusselt number follows the correlation by Peng et al.(2006) ($Nu=0.162Ra^{0.286}$) in the 'soft' convective turbulence region ($2{\times}10^6{\leq}Ra{\leq}4{\times}10^7$) and it follows the experimental correlation by Niemela et al. (2000) ($Nu=0.124Ra^{0.309}$) in the 'hard' convective tubulence region ($10^8{\leq}Ra{\leq}10^9$) within 5% accuracy. This results show that the elliptic-blending second-moment closure with an algebraic flux model predicts very accurately the Rayleigh Benard convection.

• Nuclear Engineering and Technology
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• 제20권1호
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• pp.35-46
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• 1988

원자로의 설계나 안전성 분석을 위해서는 핵연료 집합체 내의 유동 구조와 열전달에 대한 지식이 매우 중요하다. 따라서 핵연료 집합체 내의 유체 온도 분포를 정확히 계산하기 위해서는 냉각재 유로 내에서의 속도분포를 정확히 알아야 하는데 이것은 복잡한 난류 현상 때문에 예측하기가 매우 어렵다. 본 연구는 비등방성을 고려한 2-방정식 모형을 사용하여 속도분포를 구하고 핵연료 표면에서의 균일열속을 가정하므로써 유로내에서의 속도 분포를 예측하였다. 수치해는 Galerkin유한 요소법에 의해 핵연료봉 표면까지 구하여졌다. 수치 결과는 알려진 실험치 및 계산치와 비교되어 잘 일치하고 있고, 또한 난류 비등방성이 유로 내의 평균속도와 온도분포에 영향을 미치고 있음을 보았다. 그리고 조밀한 삼각 배열 핵연료 집합체(P/D=1.05-1.3) 내에서 나트륨 냉각재를 사용한 경우의 Nu-P/D관계식을 수립하였다.

• 대한화학회지
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• 제44권5호
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• pp.442-447
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• 2000

$\alpha$-Functionalized benzylamine(Nu=OAc, OMe, $N_3$)은 유기합성의 출발물질 또는 synthon으로서 매우 유용할 것이다. 본 연구에서는 benzylphthalimide를 137$^{\circ}C$, chlorobenzene 용매 하에서 NBS/NaOAc/HOAc조건을 사용하여, 높은 수율로 phthalimide-benzyl acetate을 얻는 방법을 개발하였다. 마지막으로, phthalimide-benzyl acetate을 $NH_2NH_2$/HOAc 조건 하에서, amino(phenyl)methyl acetate (1)을 합성하였다.