• Earthquakes and Structures
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• 제3권5호
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• pp.719-747
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• 2012

In this paper a novel approach is proposed to address the problem of deriving non-stationary stochastic processes which are compatible in the mean sense with a given (target) response (uniform hazard) spectrum (UHS) as commonly desired in the aseismic structural design regulated by contemporary codes of practice. The appealing feature of the approach is that it is non-iterative and "one-step". This is accomplished by solving a standard over-determined minimization problem in conjunction with appropriate median peak factors. These factors are determined by a plethora of reported new Monte Carlo studies which on their own possess considerable stochastic dynamics merit. In the proposed approach, generation and treatment of samples of the processes individually on a deterministic basis is not required as is the case with the various "two-step" approaches found in the literature addressing the herein considered task. The applicability and usefulness of the approach is demonstrated by furnishing extensive numerical data associated with the elastic design UHS of the current European (EC8) and the Chinese (GB 50011) aseismic code provisions. Purposely, simple and thus attractive from a practical viewpoint, uniformly modulated processes assuming either the Kanai-Tajimi (K-T) or the Clough-Penzien (C-P) spectral form are employed. The Monte Carlo studies yield damping and duration dependent median peak factor spectra, given in a polynomial form, associated with the first passage problem for UHS compatible K-T and C-P uniformly modulated stochastic processes. Hopefully, the herein derived stochastic processes and median peak factor spectra can be used to facilitate the aseismic design of structures regulated by contemporary code provisions in a Monte Carlo simulation-based or stochastic dynamics-based context of analysis.

• Earthquakes and Structures
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• 제3권3_4호
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• pp.581-609
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• 2012

In this paper a novel non-iterative approach is proposed to address the problem of deriving non-stationary stochastic processes which are compatible in the mean sense with a given (target) response (uniform hazard) spectrum (UHS) as commonly desired in the aseismic structural design regulated by contemporary codes of practice. This is accomplished by solving a standard over-determined minimization problem in conjunction with appropriate median peak factors. These factors are determined by a plethora of reported new Monte Carlo studies which on their own possess considerable stochastic dynamics merit. In the proposed approach, generation and treatment of samples of the processes individually on a deterministic basis is not required as is the case with the various approaches found in the literature addressing the herein considered task. The applicability and usefulness of the approach is demonstrated by furnishing extensive numerical data associated with the elastic design UHS of the current European (EC8) and the Chinese (GB 50011) aseismic code provisions. Purposely, simple and thus attractive from a practical viewpoint, uniformly modulated processes assuming either the Kanai-Tajimi (K-T) or the Clough-Penzien (C-P) spectral form are employed. The Monte Carlo studies yield damping and duration dependent median peak factor spectra, given in a polynomial form, associated with the first passage problem for UHS compatible K-T and C-P uniformly modulated stochastic processes. Hopefully, the herein derived stochastic processes and median peak factor spectra can be used to facilitate the aseismic design of structures regulated by contemporary code provisions in a Monte Carlo simulation-based or stochastic dynamics-based context of analysis.

• 한국정보통신학회:학술대회논문집
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• 한국해양정보통신학회 2004년도 춘계종합학술대회
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• pp.327-329
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• 2004

치아 매질내에서 전파되는 광신호 해석을 위한 몬테 카를로 수치해석을 National Instrument사의 LabVIEW를 이용하여 개발하였다. 수치해석 결과 치아 조직 내 깊이에 대해 서로 다른 전파 특성을 갖는 두가지 신호를 얻었으며, 검출 신호는 약 60$\mu\textrm{m}$ 이상의 깊이에서 잡음 신호가 특성 신호에 비해 커짐으로 검출이 어려워짐을 알 수 있었다.

• Nuclear Engineering and Technology
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• 제29권5호
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• pp.375-384
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• 1997

Relative power density distributions of the Kori Unit 1 pressurized water reactor are calculated by Monte Carlo modeling with the MCNP code. The Kori Unit 1 core is modeled on a three-dimensional representation of the one-eighth of the reactor in-vessel component with reflective boundaries at 0 and 45 degrees. The axial core model is based on half core symmetry and is divided into four axial segments. Fission reaction density in each rod is calculated by following 100 cycles with 5,000 test neutrons in each cycle after starling with a localized neutron source and ten noncontributing settle cycles. Relative assembly power distributions are calculated from fission reaction densities of rods in assembly. After 100 cycle calculations, the system converges to a k value of 1.00039 $\geq$ 0.00084. Relative assembly power distribution is nearly the same with that of the Kori Unit 1 FSAR. Applicability of the full-scope Monte Carlo simulation in the power distribution calculation is examined by the relative root moan square error of 2.159%.

• Nuclear Engineering and Technology
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• 제55권8호
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• pp.2734-2741
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• 2023

Brachytherapy is a special case of radiotherapy. It should be arranged according to some principles in medical radiation applications and radiation physics. The primary principle is to use as low as reasonably achievable dose in all ionizing radiation applications for diagnostic and therapeutic treatments. Dosimetric distributions are dependent on radioactive source properties and radiation-matter interactions in an absorber medium such as phantom or tissue. In this consideration, the geometrical structure and material of the seed capsule, which surrounds a radioactive material, are directly responsible for isodose profiles and dosimetric functions. In this study, the radiometric properties of capsule material were investigated on dose distribution in a water phantom by changing its nuclear properties using the EGSnrc Monte Carlo (MC) simulation code. Effective atomic numbers of hypothetic mixtures were calculated by using different elements with several fractions for capsule material. Model 6711 brachytherapy seed was modeled by EGSnrc/Dosrcnrc Code and dosimetric functions were calculated. As a result, dosimetric parameters of hypothetic sources have been acquired in large-scale atomic number. Dosimetric deviations between the data of hypothetic seeds and the original one were analyzed. Unit dose (Gy/Particle) distributions belonging to different types of material in seed capsule have remarkably differed from the original capsule's data. Capsule type is major variable to manage the expected dose profile and isodose distribution around a seed. This study shows us systematically varied scale of material type (cross section or effective atomic number dependent) offers selective material usage in production of seed capsules for the expected isodose profile of a specific source.

• 한국콘텐츠학회논문지
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• 제15권4호
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• pp.350-356
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• 2015

본 연구의 목적은 몬테칼로 모사방법을 이용하여 소동물 전용 양전자방출단층촬영 시스템의 모듈 내 섬광체 배열 수에 따른 특성평가를 하는 것이다. 이 연구에서 제안한 소 동물 전용 양전자방출단층촬영 시스템은 모듈 내 섬광체 수를 1 ~ 8개로 구성하였으며, 섬광체 크기는 $2.0{\times}2.0{\times}10.0mm^3$ 크기의 LSO섬광결정을 사용하였고 스캐너의 직경은 100 mm로 설계하였다. 몬테칼로 시뮬레이션 방법중에 하나인GATE 코드를 이용하여 선원은 511 keV 점선원을 이용하였으며 동시계수 측정된 좌표값을 이용하여 민감도 및 사이노그램을 획득하였다. 모듈 내 섬광체 수가 적을수록 모듈 별 틈새가 줄어들어 민감도가 향상되는 결과를 보였으며, 사이노그램 결과에서도 불완전한 데이터(missing data)가 발생하지 않는 것을 알 수 있었다. 이 연구 결과는 모듈 안 섬광체 수가 적을수록 민감도 향상 및 불완전한 데이터 획득이 줄어드는 것을 증명함으로써, 소동물 전용 양전자방출단층촬영 시스템의 성능 개선을 위한 새로운 접근법을 제시한다.

• 대한방사선기술학회지:방사선기술과학
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• 제28권2호
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• pp.117-122
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• 2005

1999년 개정된 국내 원자력법 시행령 제2조 5항에 의하면 2003년부터 원전 작업종사자들에 대해 외부 피폭 선량뿐만 아니라 내부피폭 선량도 합산하여 평가하도록 하였으며 또한 각 선량평가에 대한 오차도 50% 이내로 유지되어야 한다고 규정한 바 있어 전신이나 갑상선 계측기와 같은 내부피폭선량 측정 장비의 정밀한 계측이 요구되고 있다. 이러한 국내 원자력법의 개정에 부합하여 본 연구에서는 내부피폭 선량측정 결과치의 정확도를 향상시키기 위해서 현재 개발 중인 갑상선 내부피폭선량 측정 시스템의 검출효율을 계산하기 위한 몬테카를로 모의실험 코드(CALEFF)를 개발하였으며, 이 코드를 사용하여 다양한 실험조건에서 검출효율을 계산하였다. 향후 갑상선 내부피폭선량 측정 시스템의 보정인자로 사용하고자 한다.

• 대한전자공학회논문지
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• 제27권3호
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• pp.63-71
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• 1990

Hydrodynamic model에 의해서 submicron GaAs device를 simulation 할 때 필요한 hydrodynamic model parameter 들을 Monte Carlo code를 개발하여 추출하였다. GaAs 전도대의 밴드구조로 $\Gamma$, L, X세개의 valley를 고려하였고, 산란기구로는 polar optic phonon, acoustic phonon, equivalent intervalley, non-equivalent intervalley, ionized impurity 및 piezoelectric scattering을 고려하였다. 계산으로부터 얻은 속도 - 전계 곡선은 실험결과와 잘 일치하였고, 다른 연구자들이 소자 시뮬레이션에 사용할 수 있도록 모델 파라메터들을 표로 제시하였다.

• Journal of Astronomy and Space Sciences
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• 제15권2호
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• pp.341-358
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• 1998

천문대 X-선 연구팀에서는 검출기 내부잡음을 줄이기 위해, 반-동시 계수법을 채택하는 다중 셀 비례계수를 개발할 예정이다. 이러한 계수기의 X-선 검출효율 결정을 위해, 몬테카를로 법을 이용하는 수치모의실험 프로그램을 개발하였다. 이 프로그램을 이용하여 Ginga/LAC의 검출효율을 재현할 수 있었고, 그럼으로 해서 수치모의 실험 방법에 대한 검증을 할 수 있었다. 이 논문에서는 천문대에서 고려하고 있는 비례계수기에 대한 수치모의실험 결과들을 보고한다.

• Nuclear Engineering and Technology
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• 제54권9호
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• pp.3317-3323
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• 2022

Half Value Layer calculations theoretically need prior specification of linear attenuation calculations, since the HVL value is derived by dividing ln(2) by the linear attenuation coefficient. The purpose of this study was to establish a direct computational model for determining HVL, a vital parameter in nuclear radiation safety studies and shielding material design. Accordingly, a typical gamma-ray transmission setup has been modeled using MCNPX (version 2.4.0) general-purpose Monte Carlo code. The MCNPX code's INPUT file was designed with two detection locations for primary and secondary gamma-rays, as well as attenuator material between those detectors. Next, Half Value Layer values of some well-known gamma-ray shielding materials such as lead and ordinary concrete have been calculated throughout a broad gamma-ray energy range. The outcomes were then compared to data from the National Institute of Standards and Technology. The Half Value Layer values obtained from MCNPX were reported to be highly compatible with the HVL values obtained from the NIST standard database. Our results indicate that the developed INPUT file may be utilized for direct computations of Half Value Layer values for nuclear safety assessments as well as medical radiation applications. In conclusion, advanced simulation methods such as the Monte Carlo code are very powerful and useful instruments that should be considered for daily radiation safety measures. The modeled MCNPX input file will be provided to the scientific community upon reasonable request.