• Proceeding of EDISON Challenge
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• 2014.03a
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• pp.225-235
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• 2014

6종의 Intermediate filament 중 type IV인 Neurofilaments (NFs)는 신경세포에 존재하는 세포골격세사로 heavy NF(NF-H), medium NF(NF-M), light NF(NF-L) 세가지의 분자 질량 단백질로 구성되어 있다. NF의 side arm은 interfilament spacing과 axonal caliber를 조절하는 중요한 역할을 한다고 생각되어왔다. 또한 이에 대해서 각각의 protein의 역할은 알아내기 위해 isolated NF의 형태와 구조에 대해 많은 연구가 이루어졌는데, NF의 구조적 특성은 NF sidearm의 tail 부분에서 phosphorylation의 정도에 따른 Lys-Ser-Pro(KSP) repeats의 charge distribution을 통해 알 수 있다. 지금까지 NF에 대한 많은 연구가 이루어졌지만 인간에 한해서만 진행되었다. 그렇기 때문에 본 연구에서는 주어진 amino acid sequence와 각 species의 NF-H:NF-M:NF-L의 비율의 정보를 이용하여 The constant-NVT ensemble MC simulation을 통해 인간뿐만이 아닌 다른 species에 대한 NF의 구조적 특성을 알아보고자 한다.

• Progress in Medical Physics
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• v.33 no.4
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• pp.129-135
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• 2022

Purpose: A full-energy-peak (FEP) efficiency correction is required through a Monte Carlo simulation for accurate radioactivity measurement, considering the geometrical characteristics of the detector and the sample. However, a relative deviation (RD) occurs between the measurement and calculation efficiencies when modeling using the data provided by the manufacturers due to the randomly generated dead layer. This study aims to optimize the structure of the detector by determining the dead layer thickness based on Monte Carlo simulation. Methods: The high-purity germanium (HPGe) detector used in this study was a coaxial p-type GC2518 model, and a certified reference material (CRM) was used to measure the FEP efficiency. Using the MC N-Particle Transport Code (MCNP) code, the FEP efficiency was calculated by increasing the thickness of the outer and inner dead layer in proportion to the thickness of the electrode. Results: As the thickness of the outer and inner dead layer increased by 0.1 mm and 0.1 ㎛, the efficiency difference decreased by 2.43% on average up to 1.0 mm and 1.0 ㎛ and increased by 1.86% thereafter. Therefore, the structure of the detector was optimized by determining 1.0 mm and 1.0 ㎛ as thickness of the dead layer. Conclusions: The effect of the dead layer on the FEP efficiency was evaluated, and an excellent agreement between the measured and calculated efficiencies was confirmed with RDs of less than 4%. It suggests that the optimized HPGe detector can be used to measure the accurate radioactivity using in dismantling and disposing medical linear accelerators.

• Journal of the Institute of Electronics Engineers of Korea SD
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• v.38 no.11
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• pp.771-780
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• 2001

It is indispensable to use the process and device simulation tool in order to analyze accurately the electrical characteristics of ULSI CMOS devices, in addition to developing and manufacturing those devices. The 3D Monte Carlo (MC) simulation result is not efficient for large-area application because of the lack of simulation particles. In this paper is reported a new efficient simulation strategy for 3D MC ion implantation into large-area application using the 3D MC code of TRICSI(TRansport Ions into Crystal Silicon). The strategy is related to our newly proposed split-trajectory method and ion-splitting method(ion-shadowing approach) for 3D large-area application in order to increase the simulation ions, not to sacrifice the simulation accuracy for defects and implanted ions. In addition to our proposed methods, we have developed the cell based 3D interpolation algorithm to feed the 3D MC simulation result into the device simulator and not to diverge the solution of continuous diffusion equations for diffusion and RTA(rapid thermal annealing) after ion implantation. We found that our proposed simulation strategy is very computationally efficient. The increased number of simulation ions is about more than 10 times and the increase of simulation time is not twice compared to the split-trajectory method only.

• Nuclear Engineering and Technology
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• v.50 no.5
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• pp.673-682
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• 2018

One of the most widely used methods to estimate core damage during a nuclear power plant accident is containment radiation measurement. The evolution of severe accidents is extremely complex, leading to uncertainty in the containment dose rate (CDR). Therefore, it is difficult to accurately determine core damage. This study proposes to conduct uncertainty analysis of CDR for core damage assessment. First, based on source term estimation, the Monte Carlo (MC) and point-kernel integration methods were used to estimate the probability density function of the CDR under different extents of core damage in accident scenarios with late containment failure. Second, the results were verified by comparing the results of both methods. The point-kernel integration method results were more dispersed than the MC results, and the MC method was used for both quantitative and qualitative analyses. Quantitative analysis indicated a linear relationship, rather than the expected proportional relationship, between the CDR and core damage fraction. The CDR distribution obeyed a logarithmic normal distribution in accidents with a small break in containment, but not in accidents with a large break in containment. A possible application of our analysis is a real-time core damage estimation program based on the CDR.

• Geomechanics and Engineering
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• v.18 no.6
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• pp.595-603
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• 2019

A modified model combining Kriging and Monte Carlo method (MC) is proposed for probabilistic estimation of tunnel face stability in this paper. In the model, a novel uniform design is adopted to train the Kriging, instead of the existing active learning function. It has advantage of avoiding addition of new training points iteratively, and greatly saves the computational time in model training. The kinematic approach of limit analysis is employed to define the deterministic computational model of face failure, in which the Hoek-Brown failure criterion is introduced to account for the nonlinear behaviors of rock mass. The trained Kriging is used as a surrogate model to perform MC with dramatic reduction of calls to actual limit state function. The parameters in Hoek-Brown failure criterion are considered as random variables in the analysis. The failure probability is estimated by direct MC to test the accuracy and efficiency of the proposed probabilistic model. The influences of uncertainty level, correlation relationship and distribution type of random variables are further discussed using the proposed approach. In summary, the probabilistic model is an accurate and economical alternative to perform probabilistic stability analysis of tunnel face excavated in spatially random Hoek- Brown media.

• Nuclear Engineering and Technology
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• v.54 no.1
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• pp.30-35
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• 2022

In a nuclear reactor, gamma radiation is the dominant energy deposition in non-fuel regions. Heat is generated upon gamma deposition and consequently affects the mechanical and thermal structure of the material. Therefore, the safety of samples should be carefully considered so that their integrity and quality can be retained. To evaluate relevant parameters, an in-core gamma thermometer (GT) was used to measure gamma heating (GH) throughout the operation of the McMaster nuclear reactor (MNR) at four irradiation sites. Additionally, a Monte Carlo reactor physics code (Serpent-2) was utilized to model the MNR with the GT located in the same irradiation sites used in the measurement to verify its predictions against measured GH. This research aids in the development of modeling, calculation, and prediction of the GH utilizing Serpent-2 as well as implementing a new GH measurement at the MNR core. After all uncertainties were quantified for both approaches, comparable GH profiles were observed between the measurements and calculations. In addition, the GH values found in the four sites represent a strong level of radiation based on the distance of the sample from the core. In this study, the maximum and minimum GH values were found at 0.32 ± 0.05 W/g and 0.15 ± 0.02 W/g, respectively, corresponding to 320 Sv/s and 150 Sv/s. These values are crucial to be considered whenever sample is planned to be irradiated inside the MNR core.

• Journal of the Korean Institute of Gas
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• v.14 no.4
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• pp.31-36
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• 2010

An alternative method is presented for predicting failure probability of pipelines with corrosion defects in this paper. The failure of corroded pipeline occurs when the operating pressure is grater than the remaining strength of the pipeline, and a limit state function can be defined as the differences between the remaining strength and the operating pressure. Then, based on structural reliability theory, we can estimate the failure probability of corroded pipeline, which is dependent on elapsed time of the pipeline with active corrosion defects. In this study, a root finding (RF) method has been adopted to solve the limit state function instead of Monte-Carlo simulation (MCS) method which traditionally has been employed to solve those kinds of problems. The calculation results shows that there are only small differences between the RF and the MCS method but the RF has higher efficiency in calculation than the MCS.

• Journal of Korea Water Resources Association
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• v.42 no.10
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• pp.773-783
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• 2009

The effects of rainfall input uncertainty on predictions of stream flow are studied based extended GLUE (Generalized Likelihood Uncertainty Estimation) approach. The uncertainty in the rainfall data is implemented by systematic/non-systematic rainfall measurement analysis in Weida catchment, Germany. PDM (Probability Distribution Model) rainfall runoff model is selected for hydrological representation of the catchment. Using general correction procedure and DUE(Data Uncertainty Engine), feasible rainfall time series are generated. These series are applied to PDM in MC(Monte Carlo) and GLUE method; Posterior distributions of the model parameters are examined and behavioural model parameters are selected for simplified GLUE prediction of stream flow. All predictions are combined to develop ensemble prediction and 90 percentile of ensemble prediction, which are used to show the effects of uncertainty sources of input data and model parameters. The results show acceptable performances in all flow regime, except underestimation of the peak flows. These results are not definite proof of the effects of rainfall uncertainty on parameter estimation; however, extended GLUE approach in this study is a potential method which can include major uncertainty in the rainfall-runoff modelling.

• Journal of the Korean Vacuum Society
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• v.16 no.1
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• pp.7-14
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• 2007

A new horizontal neutron reflectometer has been designed and now under construction at the HANARO, 30 MW research reactor, in Daejon, Korea. We performed simulations of neutron ray-tracing to evaluate the performance of all of the optical components of the instrument with a Monte Carlo technique using McStas. The feasible wavelength of the incident neutron beam is $2.5{\AA}$. It produces a q-range up to $0.126{\AA}^{-1}$ with a supermirror as a deflector. Our studies showed improvement of the performance of the guide tube and monochromators. Although the performance is limited in q-range, it promises to be the first reflectometer in Korea for the study of free surfaces, which is currently in demand.

• Proceedings of the Korea Water Resources Association Conference
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• 2009.05a
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• pp.991-995
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• 2009

최근 기후변화 등으로 우리나라의 경우 강수일수는 감소한 반면 집중호우의 발생빈도는 증가하고 있다. 실제 가뭄과홍수와 같은 극치사상의 피해가 증가될 가능성과 이러한 재해로부터 인명 및 재산을 보호하고 효율적인 수자원 활용을 위해서는 장기간 강우-유출과정의 정확한 해석이 필수적이다. 본 연구는 미호천 유역을 대상으로 장기유출을 모의하기 위해 개념적 강우유출모형을 적용하였다. 본 연구의 개념적 강우유출모형은 PDM(Probability Distributed Model)으로 유역을 한 개의 단위구역으로 사용한 집중형(lumped) 모형이고, 분포형 모형에 비하여 간단 (parsimonious)하며 영국의 수자원 및 홍수 관리 목적으로 널리 사용되고 있다. 모형의 검정은 MC(Monte Carlo) 방법과 SCE-UA(Shuffled Complex Evolution-University of Arizona) 방법을 적용하였으며, NSE(Nash Sutcliffe Efficiency) 목적함수를 사용하여 모형의 성능을 검토하였다. 그 결과, MC 방법과 SCE-UA 방법 모두 NSE의 값 0.9 이상으로 만족할 만한 모의성능을 나타내었다. 분포형 모형에 비하여 적은 수문자료 및 검정변수를 갖는 PDM 모형을 수문자료의 취득이 용이하지 않은 중 소규모 유역에 적용하여 모형의 검정 및 유량산정에 있어 우수함을 확인하였다. 이에 우리나라 전역에 걸쳐 다양한 유역을 대상으로 PDM 모형의 검토가 요구되고, 향후 우리나라의 홍수량 산정 및 수자원 관리에 적용될 수 있다고 판단된다.