• 한국의학물리학회:학술대회논문집
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• 한국의학물리학회 2002년도 Proceedings
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• pp.106-108
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• 2002

Recent advances in radiation transport algorithms, computer hardware performance, and parallel computing make the clinical use of Monte Carlo based dose calculations possible. Monte Carlo treatment planning requires accurate beam information as input to generate accurate dose distributions. The procedures to obtain this accurate beam information are called "commissioning", which includes accelerator head modeling. In this study, we would like to investigate how much accurately Monte Carlo based dose calculations can predict the measured beam data in various conditions. The Siemens 6MV photon beam and the BEAM Monte Carlo code were used. The comparisons including the percentage depth doses and off-axis profiles of open fields and wedges, output factors will be presented.

• Nuclear Engineering and Technology
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• 제53권9호
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• pp.3044-3050
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• 2021

This study offers a Monte Carlo alternative for computing mass energy absorption coefficients of any material through calculation of photon energy deposited per mass of the sample and the energy flux obtained inside a sample volume. This approach is applied in this study to evaluate mass energy absorption coefficients of some amino acids found in human body at twenty-eight different photon energies between 10 keV and 20 MeV. The simulations involved a pencil beam source modeled to emit a parallel beam of mono-energetic photons toward a 1 mean free path thick sample of rectangular parallelepiped geometry. All the components in the problem geometry were surrounded by a 100 cm vacuum sphere to avoid any interactions in materials other than the absorber itself. The results computed using the Monte Carlo radiation transport packages MCNP6.2 and GAMOS5.1 were checked against the theoretical values available from the tables of XMUDAT database. These comparisons indicate very good agreement and support the conclusion that Monte Carlo technique utilized in this fashion may be used as a computational tool for determining the mass energy absorption coefficients of any material whose data are not available in the literature.

• Nuclear Engineering and Technology
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• 제55권12호
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• pp.4685-4694
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• 2023

The ability to calculate the material density sensitivity coefficients of power with respect to the material density has broad application prospects for accelerating Monte Carlo-Thermal Hydraulics iterations. The second-order material density sensitivity coefficients for the general Monte Carlo score have been derived based on the differential operator sampling method in this paper, and the calculation of the sensitivity coefficients of cell power scores with respect to the material density has been realized in continuous-energy Monte Carlo code RMC. Based on the power-density sensitivity coefficients, the sensitivity coefficients of power scores to some other physical quantities, such as power-boron concentration coefficients and power-temperature coefficients considering only the thermal expansion, were subsequently calculated. The effectiveness of the proposed method is demonstrated in the power-density coefficients problems of the pressurized water reactor (PWR) moderator and the heat pipe reactor (HPR) reflectors. The calculations were carried out using RMC and the ENDF/B-VII.1 neutron nuclear data. It is shown that the calculated sensitivity coefficients can be used to predict the power scores accurately over a wide range of boron concentration of the PWR moderator and a wide range of temperature of HPR reflectors.

• 대한전자공학회:학술대회논문집
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• 대한전자공학회 2000년도 하계종합학술대회 논문집(2)
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• pp.326-329
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• 2000

In this paper, a complete methodology of incorporating the displacement current for the calculation of a single electron inverter characteristics has been devised. It has been implemented for the calculation of the low frequency noise spectrum in a single electron inverter in the framework of Monte-Carlo method. Our new methodology opens up a systematic way of analyzing transient behaviors of single electron circuits.

• 한국의학물리학회:학술대회논문집
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• 한국의학물리학회 2002년도 Proceedings
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• pp.291-293
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• 2002

Accurate dose calculation in radiation treatment planning is most important for successful treatment. Since human body is composed of various materials and not an ideal shape, it is not easy to calculate the accurate effective dose in the patients. Many methods have been proposed to solve the inhomogeneity and surface contour problems. Monte Carlo simulations are regarded as the most accurate method, but it is not appropriate for routine planning because it takes so much time. Pencil beam kernel based convolution/superposition methods were also proposed to correct those effects. Nowadays, many commercial treatment planning systems, including Pinnacle and Helax-TMS, have adopted this algorithm as a dose calculation engine. The purpose of this study is to verify the accuracy of the dose calculated from pencil beam kernel based treatment planning system Helax-TMS comparing to Monte Carlo simulations and measurements especially in inhomogeneous region. Home-made inhomogeneous phantom, Helax-TMS ver. 6.0 and Monte Carlo code BEAMnrc and DOSXYZnrc were used in this study. Dose calculation results from TPS and Monte Carlo simulation were verified by measurements. In homogeneous media, the accuracy was acceptable but in inhomogeneous media, the errors were more significant.

• Nuclear Engineering and Technology
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• 제50권6호
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• pp.854-859
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• 2018

Calculating minimal cut sets is a typical quantification method used to evaluate the top event probability for a fault tree. If minimal cut sets cannot be calculated or if the accuracy of the quantification result is in doubt, the Monte Carlo method can provide an alternative for fault tree quantification. The Monte Carlo method for fault tree quantification tends to take a long time because it repeats the calculation for a large number of samples. Herein, proposal is made to improve the quantification algorithm of a fault tree with circular logic. We developed a top-down iteration algorithm that combines the characteristics of the top-down approach and the iteration approach, thereby reducing the computation time of the Monte Carlo method.

• 한국음향학회지
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• 제21권3호
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• pp.221-229
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• 2002

본 논문에서는 Monte-Carlo 방법으로 빔패턴 오차의 허용범위를 만족하는 개별소자의 허용오차를 규정하였다. 일반적으로 사용되는 통계적인 방법은 불규칙한 특성을 갖는 랜덤오차를 정규분포를 갖는 랜덤 변수로 모델링을 하여 개별소자의 오차범위를 규정하는데, 이러한 방법은 해석하고자 하는 배열소자의 개수증가에 따라 계산량이 지수승으로 늘어나게 되어 많은 소자배열에는 적합하지 않게 된다. 이러한 단점을 보완하기 위해서 이 논문에서는 Monte-Carlo 방법을 사용하여 배열소자의 증가에 따른 계산량의 증가를 줄이는 새로운 알고리즘을 제안하였다. 그리고 이렇게 규정된 오차의 범위를 간단한 모의실험을 통해서 검증하였다.

• Nuclear Engineering and Technology
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• 제51권8호
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• pp.1998-2004
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• 2019

The Multi-Physics (MP) instrument is one of 20 neutron spectrometers planned in the China Spallation Neutron Source (CSNS). This paper presents a shielding calculation for the MP instrument using Monte Carlo codes MCNPX and FLUKA. First, the neutrons that escape from the CSNS decoupled water moderator and are delivered to the beam line of the MP instrument are calculated to use as the source term of the shielding calculation. Then, to validate the calculation method based on multiple variance reduction techniques, a cross check between MCNPX and FLUKA codes is performed by comparing the calculation results of the dose rate distribution on a simplified beam line model. Finally, a complete geometry model of the MP instrument is set up, and the primary parameters for the shielding design are obtained according to the calculated dose rate map considering different worst-case scenarios.

• Journal of Radiation Protection and Research
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• 제26권2호
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• pp.93-99
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• 2001

해부학적으로 단순한 수학적인형팬텀의 한계를 극복하기 위한 voxel 머리팬텀을 제작하고 BNCT(Boron Neutron Capture Therapy) 시행 시 선량분포를 계산하였다. 일반목적 몬테칼로 코드인 MCNP4B의 반복구조 알고리즘을 이용하여 voxel 몬테칼로 계산체계를 수립하였고 두 가지 물질로 구성된 예시적 voxel 팬텀과 기하체조합팬텀의 계산값 비교를 통해 계산체계를 검증하였다. 미국 NLM(National Library of Medicine)에서 제공하는 VHP man 인체단층사진에 대한 분할 및 색인작업을 통해 voxel 머리팬텀을 제작하여 AP 및 PA 방향에서 입사하는 넓고 평행한 광자 및 중성자빔에 대한 선량값을 MIRD 팬텀의 계산값과 비교한 결과 중성자빔 AP 방향조사 시 MIRD 팬텀에서는 볼 수 없는 안구로 인한 중성자 감쇠현상을 확인할 수 있었다. 3차원 정밀계산이 필요한 BNCT 시술시 선량분포계산을 위해 뇌 중앙에 직경 5cm의 구형 뇌종양 체적을 정의하고 뇌와 종양의 붕소 함량을 조정하여 10keV 및 40keV 상부입사 중성자에 의한 장기별 흡수선량을 계산한 결과 종양에 $30{\mu}g/g$, 정상세포에 $3{\mu}g/g$의 붕소를 주입한 경우 붕소함량이 없을 때에 비해 2배 가량 큰 선량을 보였다. 본 연구를 통해 voxel몬테칼로기법을 이용한 선량평가체계를 수립하였고 정밀한 선량계산을 필요로 하는 치료방사선분야 선량계산에 실제 인체에 가까운 voxel팬텀의 응용가능성을 제시하였다.

• 한국의학물리학회지:의학물리
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• 제16권3호
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• pp.138-147
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• 2005

몬테칼로 선량계산 시 적절한 정확도를 얻기 위해서는 계산입자수를 늘려야 하고 그로 인해 계산 시간이 오래 걸리게되므로 일상적 치료계획의 선량계산 방법으로 이용되지 못했다. 본 연구에서는 몬테칼로 모의실험 시 계산입자 수를 줄여서 선량계산을 수행한 후 잡음 감소 필터를 적용하여 선량계산 결과를 개선하고자 하였다. 이를 위해 국소 최소자승 잡음 감소 필터를 제작하고 광자선 및 전자선 균질/비균질 팬텀 내 선량계산 결과에 대하여 적용하여 선택적 여과를 수행하였으며 그 유효성을 등선량 곡선 비교 및 감마시험을 통하여 검증하였다. 연구 결과 통계적 불확실도를 2$\%$ 이내로 유지하기 위해 필요한 계산입자수의 10$\%$ 이하의 계산입자 수를 이용하여 몬테칼로 선량계산 뒤 후처리한 결과가 기준계산 입자수를 이용하여 얻은 몬테칼로 선량계산 결과와 유사해질 수 있음을 확인하였다.