• 한국방사선학회논문지
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• 제15권2호
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• pp.125-130
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• 2021

AAPM CT 성능 팬텀에서 CT수 교정 삽입부의 각 핀과 물에 대응하는 유효원자번호 및 물리적 밀도에 대한 CT수에 관한 자료가 거의 없다. 따라서 자료화의 필요성이 제기되었다. 이 연구의 목적은 AAPM CT 성능 팬텀에서 CT수 교정 삽입부의 각 핀 및 물에 대하여 유효원자번호를 산출하고, 산출된 유효원자번호 및 물리적 밀도에 대한 CT수를 측정하여 비교분석하는데 있다. AAPM CT 성능 팬텀의 CT수 교정 삽입부에서 각 핀과 물의 유효원자번호 및 물리적 밀도에 관한 CT수의 자료를 획득하기 위하여, 먼저 각 핀과 물에 대한 유효원자번호를 산출하였다. 그리고 CT스캐너로 CT수 교정 삽입부를 스캔하여 CT슬라이스들을 획득하였다. 중심 CT슬라이스에서 각 핀과 물에 대하여 CT수들을 측정하였다. 결과로서, 유효원자번호에 대한 CT수들은 유효원자번호가 증가할수록 비선형적으로 증가와 감소를 반복하는 양상을 나타내었다. 그리고 물리적 밀도에 대한 CT수들도 물리적 밀도가 증가할수록 비선형적으로 증가와 감소를 반복하는 양상을 나타내었다.

• Nuclear Engineering and Technology
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• 제44권7호
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• pp.735-744
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• 2012

In order to quantify the flow distribution characteristics of APR+ reactor, a test was performed on a test facility, ACOP ($\underline{A}$PR+ $\underline{C}$ore Flow & $\underline{P}$ressure Test Facility), having a length scale of 1/5 referring to the prototype plant. The major parameters are core inlet flow and outlet pressure distribution and sectional pressure drops along the major flow path inside reactor vessel. To preserve the flow characteristics of prototype plant, the test facility was designed based on a preservation of major flow path geometry. An Euler number is considered as primary dimensionless parameter, which is conserved with a 1/40.9 of Reynolds number scaling ratio. ACOP simplifies each fuel assembly into a hydraulic simulator having the same axial flow resistance and lateral cross flow characteristics. In order to supply boundary condition to estimate thermal margins of the reactor, the distribution of inlet core flow and core exit pressure were measured in each of 257 fuel assembly simulators. In total, 584 points of static pressure and differential pressures were measured with a limited number of differential pressure transmitters by developing a sequential operation system of valves. In the current study, reactor flow characteristics under the balanced four-cold leg flow conditions at each of the cold legs were quantified, which is a part of the test matrix composing the APR+ flow distribution test program. The final identification of the reactor flow distribution was obtained by ensemble averaging 15 independent test data. The details of the design of the test facility, experiment, and data analysis are included in the current paper.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1997년도 추계학술발표회논문집(1)
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• pp.64-69
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• 1997

The code WIMS-AECL has been used for the lattice analysis of DUPIC fuel. The lattice parameters calculated by the code is sensitive to the choice of number of parameters, such as the number of tracking lines, number of condensed groups, mesh spacing in the moderator region, other parameters vital to the calculation of probabilities and burnup analysis. We have studied this sensitivity with respect to these parameters and recommend their proper values which are necessary for carrying out the lattice analysis of DUPIC fuel.

• 대한수학회논문집
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• 제24권3호
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• pp.333-339
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• 2009

In this manuscript, we introduce the concept of an atomic subset of the hyper BCK-algebra and study its properties. Also, we give a characterization of the atomic hyper BCK-algebra and show that there are exactly (up to isomorphism) n atomic hyper BCK-algebras H with |H| = n for any natural number n.

• 한국방사선학회논문지
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• 제16권5호
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• pp.537-543
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• 2022

본 연구의 목적은 이중에너지 CT를 이용한 유효원자번호 정보를 통한 췌장 검출 가능성 연구이다. 10개의 다양한 인체 등가 물질의 유효원자번호를 Stoichiometric calibration을 통해 추정하였다. Stoichiometric calibration을 위해 저에너지와 고에너지에 해당하는 10개 인체 등가 물질에 대한 HU값을 이용하였다. 이를 바탕으로 반복 알고리즘을 통해 인체 등가 물질에 대한 유효원자번호 영상을 추출하였다. 연구결과에 따르면, 유효원자번호에 따른 감약의 비는 R²값이 0.9999로 추정되었고, Pancreas, water, Liver, Blood, Spongiosa, Cortical bone의 유효원자번호는 이론값과 비교하여 전체적으로 1% 이내의 정확도를 보였다. 췌장암 검사는 조영제를 사용하므로 잠재적인 조영제 부작용 가능성이 있다. 이를 해결하기 위해 조영 증강 없는 이중에너지를 이용한 유효원자번호 추출을 통해 정확하고 안전한 검사에 기여할 수 있을 것으로 사료된다. 본 연구를 바탕으로 향후 연구에서는 임상 영상을 바탕으로 췌장암의 HU값을 이용하여 췌장암 검출에 대한 연구를 수행할 것이다.

• Nuclear Engineering and Technology
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• 제38권4호
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• pp.353-358
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• 2006

Alpha track analysis for the determination of the trace amount of alpha emitting nuclides in a very small particle was performed as an efficient and powerful technique during safeguard inspection. Metal particles with well-defined spherical shape, size and isotopic compositions as a reference material were used to correlate the number of tracks or track diameter with an isotopic composition eventually to identify the uranium enrichment in the environmental swipe samples. Slopes in the number of tracks versus the exposure time curve provide a simple insight into the uranium enrichment of an unknown particle. Low enriched uranium metal particles result in slopes still steeper than the depleted or natural uranium metal particles. In addition, a linear relationship between track diameter and particle size Is thought to be a useful first stage analytical tool as an efficient and convenient inspection guide. The significance of the simple linear model was also judged using the usual statistical tests.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2004년도 추계학술발표회 발표논문집
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• pp.205-206
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• 2004

• Journal of Mechanical Science and Technology
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• 제18권10호
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• pp.1782-1798
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• 2004

A numerical study of a natural convection in a rectangular cavity with the low-Reynolds-number differential stress and flux model is presented. The primary emphasis of the study is placed on the investigation of the accuracy and numerical stability of the low-Reynolds-number differential stress and flux model for a natural convection problem. The turbulence model considered in the study is that developed by Peeters and Henkes (1992) and further refined by Dol and Hanjalic (2001), and this model is applied to the prediction of a natural convection in a rectangular cavity together with the two-layer model, the shear stress transport model and the time-scale bound ν$^2$- f model, all with an algebraic heat flux model. The computed results are compared with the experimental data commonly used for the validation of the turbulence models. It is shown that the low-Reynolds-number differential stress and flux model predicts well the mean velocity and temperature, the vertical velocity fluctuation, the Reynolds shear stress, the horizontal turbulent heat flux, the local Nusselt number and the wall shear stress, but slightly under-predicts the vertical turbulent heat flux. The performance of the ν$^2$- f model is comparable to that of the low-Reynolds-number differential stress and flux model except for the over-prediction of the horizontal turbulent heat flux. The two-layer model predicts poorly the mean vertical velocity component and under-predicts the wall shear stress and the local Nusselt number. The shear stress transport model predicts well the mean velocity, but the general performance of the shear stress transport model is nearly the same as that of the two-layer model, under-predicting the local Nusselt number and the turbulent quantities.

• Nuclear Engineering and Technology
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• 제38권8호
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• pp.809-818
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• 2006

The existing experimental data related to the turbulent mixing factor in rod arrays is examined and a new definition of the turbulent mixing factor is introduced to take into account the turbulent mixing of fluids with various Prandtl numbers. The new definition of the mixing factor is based on the eddy diffusivity of energy. With this definition of the mixing factor, it was found that the geometrical parameter, ${\delta}_{ij}/D_h$ correlates the turbulent mixing data better than Sid, which has been used frequently in existing correlations. Based on the experimental data for a highly turbulent condition in square rod arrays, a correlation describing turbulent mixing dependent on the parameter ${\delta}_{ij}/D_h$ has been developed. The correlation is insensitive to the Re number and it takes into account the effect of the turbulent Prandtl number. The proposed correlation predicts a reasonable mixing even at a lower S/d ratio.

• Nuclear Engineering and Technology
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• 제49권7호
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• pp.1571-1574
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• 2017

In the present work, the gamma ray backscattering technique was used to determine the effective atomic numbers for certain binary alloys. With the help of a muffle furnace, the binary alloys were synthesized using the melt quenching technique with different compositions of $_{82}Pb$, $_{50}Sn$, and $_{30}Zn$. The intensity distribution of backscattered photons from radioactive isotope $^{22}Na$ (511 keV) was recorded with the help of GAMMARAD5 [$76mm{\times}76mm$ NaI(Tl) scintillator detector] and analyzed as a function of both atomic number and thickness of the target material. The effective atomic numbers for the same binary alloys were also computed theoretically using the atomic to electronic cross-section method with the help of the mass attenuation coefficient database of WinXCom (2001). Good agreement was observed between theoretical and experimental results for the effective atomic numbers of all the selected alloys.