• 한국통신학회논문지
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• 제17권10호
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• pp.1147-1156
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• 1992

본 논문에서는 $\pi/4$ shift QPSK에 Trellis 부호화된 변조 기법(Trellis-Coded Modulation. TCM)을 적용시키기위하여 $\pi/8$ shift 8PSK를 제안하고 위상차에 의한 신호 집합 확장과 신호 집합 분할을 수행하는 trellis 부호화된 π/8 shift 8PSK를 제안한다. 또한 BER(Bit Error Rate) 성능을 향상시키기위하여 제1차 위상차뿐만아니라 제L차 이상차의 자승 유클리드 거리를 매트릭(Branch Metric)으로 갖는 비터비 디코더(Viterbi decoder)를 설계한다. 그리고 $\pi/4$ shift QPSK, trellis 부호화된 $\pi/8$ shift 8PSK와 제L차 위상차의 자승 유클리드 거리를 메트릭(Branch Metric)으로 갖는 trellis 부호화된 $\pi/8$ shift 8PSK 의 BER 특성을 AWGN에서 Monte Carlo 시뮬레이션을 통해 알아본다. 제안된 알고리즘은 MDPSK에도 적용될 수 있다.

• 한국방사선학회논문지
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• 제15권4호
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• pp.415-427
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• 2021

한국원자력의학원에서는 50 MeV 사이클로트론의 빔 라인을 이용하여 연구자들에게 다양한 빔 조사 서비스를 수행하고 있다. 특히 중성자 빔 서비스는 양성자와 베릴륨의 핵반응을 이용하기 때문에 높은 전류를 사용하므로 조사 시료의 방사화 가능성이 높아진다. 본 연구에서는 연구자들이 선호하는 35 MeV 20 ㎂ 중성자 빔 서비스에 의해 발생 가능한 방사화에 대해 MCNP 6.2와 FISPACT-II 4.0을 이용해 평가했다. 평가결과 철, 구리, 텅스텐 시료는 1시간 이상 조사하는 경우 장반감기 핵종이 생성되는 방사화가 발생하여 자체처분농도를 초과했다. 매일 2시간 사용 조건에서 건축물에 대한 방사화는 발생하지 않았고 조사실 내부 공기의 방사화로 인한 종사자의 내부피폭은 매우 미비했고, 이 공기를 배기하는 경우 배출기준도 만족했다.

• 한국추진공학회:학술대회논문집
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• 한국추진공학회 2011년도 제37회 추계학술대회논문집
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• pp.769-771
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• 2011

KSLV-I 2단에 탑재된 위성은 KM과 충돌하지 않도록 오염 및 충돌 회피 기동(CCAM)을 수행하게 된다. 이때 위성이 KM 잔류 추력 Plume의 밀도가 충분히 낮은 영역을 통과해야만 오염을 피할 수 있으며, 이를 확인하기 위해서는 Plume 유동장의 정확한 예측이 필수적이다. 본 논문에서는 다양한 희박기체 유동해석에 사용되어 그 정확도가 검증된 DSMC 기법을 사용하는 러시아 ITMA 연구소의 SMILE Code를 이용하여 위성과 분리된 KM의 잔류추력에 의한 Plume의 밀도장을 시뮬레이션 하여 분포를 예측하였고, 그 결과의 신뢰성을 확인하기 위하여 KM 노즐 내부의 밀도장은 Fluent의 결과와 비교하여 그 타당성을 입증하였다.

• Nuclear Engineering and Technology
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• 제54권12호
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• pp.4731-4742
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• 2022

RBMK fuel assemblies differ from other LWR FA due to a specific arrangement of the fuel rods, the low enrichment, and the used burnable absorber - erbium. Therefore, there is a challenge to adapt modeling tools, developed for other LWR types, to solve RBMK problems. A set of 10 different depletion simulation schemes were tested to estimate the impact on reactivity and spent fuel composition of possible SCALE code options for the neutron transport modelling and the use of different nuclear data libraries. The simulations were performed using cross-section libraries based on both, VII.0 and VII.1, versions of ENDF/B nuclear data, and assuming continuous energy and multigroup simulation modes, standard and user-defined Dancoff factor values, and employing deterministic and Monte Carlo methods. The criticality analysis with burn-up credit was performed for the SFP loaded with RBMK-1500 FA. Spent fuel compositions were taken from each of 10 performed depletion simulations. The criticality of SFP is found to be overestimated by up to 0.08% in simulation cases using user-defined Dancoff factors comparing the results obtained using the continuous energy library (VII.1 version of ENDF/B nuclear data). It was shown that such discrepancy is determined by the higher U-235 and Pu-239 isotopes concentrations calculated.

• Nuclear Engineering and Technology
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• 제52권4호
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• pp.661-673
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• 2020

The quarter-core simulation of BEAVRS Cycle 2 depletion benchmark has been conducted using the MCS/CTF coupling system. MCS/CTF is a cycle-wise Picard iteration based inner-coupling code system, which couples sub-channel T/H (thermal/hydraulic) code CTF as a T/H solver in Monte Carlo neutron transport code MCS. This coupling code system has been previously applied in the BEAVRS benchmark Cycle 1 full-core simulation. The Cycle 2 depletion has been performed with T/H feedback based on the spent fuel materials composition pre-generated by the Cycle 1 depletion simulation using refueling capability of MCS code. Meanwhile, the MCS internal one-dimension T/H solver (MCS/TH1D) has been also applied in the simulation as the reference. In this paper, an analysis of the detailed criticality boron concentration and the axially integrated assembly-wise detector signals will be presented and compared with measured data based on the real operating physical conditions. Moreover, the MCS/CTF simulated results for neutronics and T/H parameters will be also compared to MCS/TH1D to figure out their difference, which proves the practical application of MCS into the BEAVRS benchmark two-cycle depletion simulations.

• Nuclear Engineering and Technology
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• 제19권2호
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• pp.85-98
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• 1987

중대사고시 LMFBR의 에어로졸(aerosol) 동특성을 살피기 위해 전산코드인 MCAD (Multicomponent Aerosol Dynamics)가 개발되었다. 사고경과에 따른 두 방사능원의 상대적인 충돌확률을 적용하여 에어로졸계를 모사할 수 있다. Brownian 확산과 중력작용에 의한 결합 및 제거과정을 고려했으며, 입자형태를 묘사하기 위해 밀도보정과 형태요소(shape factor)를 동시에 고려하였다. ORNL의 NSPP-300 계열 실험자료와 기존의 코드를MCAD의 입증에 이용하였다. 그 결과 MCAD의 계산치와 실험치 및 기존의 코드 계산값이 일치함을 보여준다. 여러 입력자료의 불화실한 값들을 정의하고, 그들값의 한계로 설정하기 위하여 불확실성 및 민감도해석을 수행하였다. 14개의 입력자료를 선택하여 실험계획법과 Latin hypercube sampling에 의한 입력자료를 조합하여 그 회귀 (regression) 정도를 반응표면 계획법(Response surface method)에 의해 구하였다. 각 변수들의 중요성 및 시간경과에 따른 그들의 상대적인 등위를 결정하기 위하여 단계식 회귀방법 (Stepwise regression method)을 고려했다. LHS에 의한 회귀모형에 Monte Carlo Method를 적용하여 계산값 및 변수들에의 신뢰도를 향상시켰다.

• Journal of Korean Vacuum Science & Technology
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• 제1권1호
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• pp.1-12
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• 1997

A new three-dimensional (3D) Monte Carlo ion implantation simulator, TRICSI, has been developed to investigate 3D mask effects in the typical mask structure for ion implantation into crystalline silicon. We present the mask corner and mask size effects of implanted boron range profiles, and also show the calculated damage distributions by applying the modified Kinchin-Pease equation in the single-crystal silicon target. The simulator calculates accurately and efficiently the implanted-boron range profiles under the relatively large implanted area, using a newly developed search algorithm for the collision partner in the single-crystal silicon. All of the typical implant parameters such as dose, tilt and rotation angles, in addition to energy can be used for the 3D simulation of ion implantation.

• 한국안전학회지
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• 제32권2호
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• pp.34-37
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• 2017

In recent emerging industry, Display field becomes bigger and bigger, and also semiconductor technology becomes high density integration. In Flat Panel Display, there is an issue that electrostatic phenomenon results in fine dust adsorption as electrostatic capacity increases due to bigger size. Destruction of high integrated circuit and pattern deterioration occur in semiconductor and this causes the problem of weakening of thermal resistance. In order to solve this sort of electrostatic failure in this process, Soft X-ray ionizer is mainly used. Soft X-ray Ionizer does not only generate electrical noise and minute particle but also is efficient to remove electrostatic as it has a wide range of ionization. X-ray Generating efficiency has an effect on soft X-ray Ionizer affects neutralizing performance. There exist variable factors such as type of anode, thickness, tube voltage etc., and it takes a lot of time and financial resource to find optimal performance by manufacturing with actual X-ray tube source. MCNPX (Monte Carlo N-Particle Extended) is used for simulation to solve this kind of problem, and optimum efficiency of X-ray generation is anticipated. In this study, X-ray generation efficiency was measured according to target material thickness using MCNPX under the conditions that tube voltage is 5 keV, 10 keV, 15 keV and the target Material is Tungsten(W), Gold(Au), Silver(Ag). At the result, Gold(Au) shows optimum efficiency. In Tube voltage 5 keV, optimal target thickness is $0.05{\mu}m$ and Largest energy of Light flux appears $2.22{\times}10^8$ x-ray flux. In Tube voltage 10 keV, optimal target Thickness is $0.18{\mu}m$ and Largest energy of Light flux appears $1.97{\times}10^9$ x-ray flux. In Tube voltage 15 keV, optimal target Thickness is $0.29{\mu}m$ and Largest energy of Light flux appears $4.59{\times}10^9$ x-ray flux.

• 대한방사선기술학회지:방사선기술과학
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• 제40권1호
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• pp.93-99
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• 2017

Monte Carlo 시뮬레이션을 이용하여 MV X, ${\gamma}$선에서의 선량증가 효과를 평가하였다. MCNPX code를 이용하여 ICRU 평판형(Slab) 모의피폭체를 전산모사하였으며, 입사 광자의 에너지, 선량증가 물질의 종류 및 농도에 따른 영향을 분석하였다. 선량증가 물질은 금(aurum), 가돌리늄(gadolinium), 요오드(iodine), 산화철(iron oxide)에 대해 비교 평가하였으며, 입사에너지는 선형가속기에서 발생된 4, 6, 10, 15 MV X선의 스펙트럼과 Co 60의 ${\gamma}$선원을 사용하였다. 모의피폭체 내에 7, 18, 30 mg/g 농도의 물질을 삽입하였으며, 선량증가 효과의 정량적 평가를 위해 선량증가비를 산출하였다. X선의 입사에너지가 낮을수록, 선량증가 물질의 농도가 높을수록 높은 선량증가비를 나타내었으며, 최대 선량증가비는 금 1.079, 가돌리늄 1.062, 요오드 1.049, 산화철 1.035를 보여 금, 가돌리늄, 요오드, 산화철 입자 순으로 높은 선량증가 효과를 보였다. 이러한 결과는 In-vivo, vitro 연구의 기초자료로 활용할 수 있을 것으로 사료된다.

• Journal of Radiation Protection and Research
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• 제48권4호
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• pp.197-203
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• 2023

Background: The thermoluminescent dosimeter (TLD) and Monte Carlo (MC) dosimetry are carried out to determine the occupational dose for personnel in the handling of ¹²⁵I seed sources. Materials and Methods: TLDs were placed in different layers of the Alderson-Rando phantom in the thyroid, lung and also eyes and skin surface. An ¹²⁵I seed source was prepared and its activity was measured using a dose calibrator and was placed at two distances of 20 and 50 cm from the Alderson-Rando phantom. In addition, the Monte Carlo N-Particle Extended (MCNPX 2.6.0) code and a computational phantom with a lattice-based geometry were used for organ dose calculations. Results and Discussion: The comparison of TLD and MC results in the thyroid and lung is consistent. Although the relative difference of MC dosimetry to TLD for the eyes was between 4% and 13% and for the skin between 19% and 23%, because of the existence of a higher uncertainty regarding TLD positioning in the eye and skin, these inaccuracies can also be acceptable. The isodose distribution was calculated in the cross-section of the head phantom when the ¹²⁵I seed was at two distances of 20 and 50 cm and it showed that the greatest dose reduction was observed for the eyes, skin, thyroid, and lungs, respectively. The results of MC dosimetry indicated that for near the head positions (distance of 20 cm) the absorbed dose rates for the eye lens, eye and skin were 78.1±2.3, 59.0±1.8, and 10.7±0.7 µGy/mCi/hr, respectively. Furthermore, we found that a 30 cm displacement for the ¹²⁵I seed reduced the eye and skin doses by at least 3- and 2-fold, respectively. Conclusion: Using a computational phantom to monitor the dose to the sensitive organs (eye and skin) for personnel involved in the handling of ¹²⁵I seed sources can be an accurate and inexpensive method.