• Proceedings of the Korean Society of Medical Physics Conference
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• 2004.11a
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• pp.29-32
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• 2004

In this study, we had modelled Siemens type MLC using BEAM Monte Carlo code and tested the feasibility of the modelling. To model the Primus linac MLC, we had measured the actual dimensions of MLC and each leaves, then approximated the leaf shape. VARMLC component module was used for the modelling and leakage, tongue-and-groove effect were also considered. Simulation result showed the good agreement with the film measurement.

• Proceedings of the Korea Institute of Fire Science and Engineering Conference
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• 2011.11a
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• pp.243-247
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• 2011

본 논문에서는 원자력발전소의 화재 안전성평가에서 제기되는 화재모델링 불확실성 분석 방법을 검토하고 논의하였다. 원자력발전소의 성능기반 화재 안전성평가에 대해서는 NUREG-1934를, 확률론적 화재 안전성 평가에 대해서는 NUREG/CR-6850를 중심으로 화재 모델링 불확실성 분석 방법을 소개하고 몬테칼로 시뮬레이션을 이용한 불확실성 분석 방법에 대해 논의하였다.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.11a
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• pp.45-52
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• 1996

고리 1 호기 원자로 감시？슐에서의 고속중성자 플루언스를 계산하기 위하여 MCNP코드로 3차원 모델링을 하였다. 중성자선원은 MCNP에 의해 계산된 핵연료봉출력분포를 사용하였고 원자로심부터 원자로 압력용기 밖까지 1 MeV이상의 중성자를 수송시켰다. 감시？슐은 실제의 같은 크기로 모델링하였고 감시？슐안의 시편은 원자로 압력용기와 같은 재질의 직육면체로 가정하였다. 그리고 MCNP에 의해 감시시편내의 방사화 시료의 핵반응단면적을 계산하였다. 또한 MCNP에 의해 이론적으로 계산된 감시？슐에서 중성자 플루언스와 기존의 감시시험에서 측정된 포화방사능으로 부터 계산된 실험적 감시？슐 중성자 플루언스를 비교하였다. 이론적 ？슐플루언스와 실험적 ？슐플루언스의 비는 대체로 1.0에서 크게 벗어나지 않았으나 감시시험과 시편에 따라 크게 벗어나는 경우도 있었다. MCNP에 의한 유효반응단면적의 계산방법이 기존의 방법보다 모델링 및 계산의 불확실성을 최소화 할 수 있으므로 이번 연구에서 고려하지 못한 원자로심의 연소도를 고려한다면 매우 신뢰성이 높은 결과를 얻을 수 있다.

• Progress in Medical Physics
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• v.21 no.3
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• pp.253-260
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• 2010

Most brachytherapy treatment planning systems employ a dosimetry formalism based on the AAPM TG-43 report which does not appropriately consider tissue heterogeneity. In this study we aimed to set up a simple Monte Carlo-based intracavitary high-dose-rate brachytherapy (IC-HDRB) plan verification platform, focusing particularly on the robustness of the direct Monte Carlo dose calculation using material and density information derived from CT images. CT images of slab phantoms and a uterine cervical cancer patient were used for brachytherapy plans based on the Plato (Nucletron, Netherlands) brachytherapy planning system. Monte Carlo simulations were implemented using the parameters from the Plato system and compared with the EBT film dosimetry and conventional dose computations. EGSnrc based DOSXYZnrc code was used for Monte Carlo simulations. Each $^{192}Ir$ source of the afterloader was approximately modeled as a parallel-piped shape inside the converted CT data set whose voxel size was $2{\times}2{\times}2\;mm^3$. Bracytherapy dose calculations based on the TG-43 showed good agreement with the Monte Carlo results in a homogeneous media whose density was close to water, but there were significant errors in high-density materials. For a patient case, A and B point dose differences were less than 3%, while the mean dose discrepancy was as much as 5%. Conventional dose computation methods might underdose the targets by not accounting for the effects of high-density materials. The proposed platform was shown to be feasible and to have good dose calculation accuracy. One should be careful when confirming the plan using a conventional brachytherapy dose computation method, and moreover, an independent dose verification system as developed in this study might be helpful.

• Proceedings of the Korea Multimedia Society Conference
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• 1998.10a
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• pp.31.1-36
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• 1998

본 논문은 하이퍼미디어 시나리오 수행시간 예측 방법을 고찰한다. 시나리오 수행 시간 정보는 사용자가 본인의 시간 사용 계획 수립이나, 정보 제공자가 효율적인 정보 감상 스케쥴을 수립하여 제시하는 데 중요한 역할을 담당한다. 그럼에도 불구하고 이러한 정보를 얻는 방법에 대한 연구는 [1]과 [2]에 소개된 두 가지 밖에 없다. 이 두가지 방법은 모두 변형된 페트리 넷을 이용하여 시나리오를 모델링 한 다음, [1]은 몬테칼로 시뮬레이션 방법을 적용하고 [2]는 통계적 기대값을 이용한다. 본 논문에서는 이 두가지 방법을 소개한다.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05a
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• pp.905-910
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• 1995

영광 3·4호기 원자로 압력용기에 대한 고속중성자 조사량을 계산하기 위하여 MCNP코드로 3차원 모델링을 하였다. 중성자선원은 출력분포에 의해 핵연료집합제 단위로 하였고 원자로심부터 원자로 압력용기 밖까지 핵분열 반응을 포함한 모든 반응에 대해 중성자를 수송시켰다. 원자로 압력용기 안쪽 면에서의 고속중성자 플루언스는 기존의 연구자와 비교할 때 큰 차이가 있었다. 그러나 이번 연구의 계산방법이 보다 신뢰할 수 있기 때문에 앞으로의 연구를 통하여 기존의 연구방법과 비교하는 것이 필요하다.

• Fire Science and Engineering
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• v.26 no.2
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• pp.40-52
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• 2012

This paper presents the uncertainty analysis results of fire modeling input parameters for motor control center in switchgear room of nuclear power plants. FDS (Fire Dynamics simulator) 5.5 was used to simulate the fire scenario and Latin Hyper Cube Monte Carlo simulations were employed to generate random samples for FDS input parameters. The uncertainty analysis results of input parameters are compared with those of the model uncertainty analysis and sensitivity analysis approaches of NUREG-1934. The study results show that the input parameter uncertainty analysis approach may lead to more conservative results than the uncertainty analysis and sensitivity analysis methods of NUREG-1934.

• Journal of Korean Society of Steel Construction
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• v.13 no.5
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• pp.467-476
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• 2001

The construction of highway bridges is almost complete in many countries including the United States. The government and highway agencies change the focus from constructing to maintaining To maintain the bridges effectively there is an urgent need to assess actual bridge loading carrying capacity and to predict their remaining life. The system reliability techniques have to be used for this purpose. Based on lifetime distribution (function) techniques this study illustrates how typical highway bridges can be modeled to predict their remaining life. The parameters of lifetime distribution are generated by Monte. The results can be used for optimization of planning interventions on existing bridges.

• The Journal of the Acoustical Society of Korea
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• v.36 no.3
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• pp.202-210
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• 2017

For the target tracking in cluttered environment using a bistatic sonar whose transmitter and receiver are separately positioned, it is necessary to use data association algorithm via applying a proper measurement modelling to the bistatic sonar. The measurements obtained from the interval of ownship's maneuver have an increased error due to uncertainty of the position of transmitter and receiver. Using the measurements from this interval results in poor target tracking performance. In this paper, an improved tracking performance for the proposed data association based multiple model algorithm is validated by a monte carlo simulation.

• Journal of the Korea Institute of Building Construction
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• v.20 no.2
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• pp.129-135
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• 2020

The purpose of this research is to analyze the gamma ray shielding effect of heavy concrete containing magnetic aggregate and to confirm the applicability to the military protective facilities. In general, a military concrete structure protects combatants from bullets, and also it provides some radiation shielding. In this research, experiments were conducted using a Cs-137 source to check the gamma ray shielding effect. In addition, the Monte Carlo N-Particle(MCNP) modeling was applied to evaluate the gamma ray shielding effect of a military structure. As a result, as the concrete thickness increased, the shielding performance improved according th the linear attenuation law. With that, as the ratio of magnetic aggregate was increased, gamma ray shielding performance was also improved. Therefore, this research verified that the application of magnetic aggregate concrete to military facilities for radiation shielding purposes would be useful.