• Nuclear Engineering and Technology
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• 제49권7호
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• pp.1505-1512
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• 2017

Because accelerator-based boron neutron capture therapy (BNCT) systems are planned for use in hospitals, entry into the medical room should be controlled as hospitals are generally assumed to be public and safe places. In this paper, computational investigation of the medical staff effective dose during BNCT has been performed in different situations using Monte Carlo N-Particle (MCNP4C) code and two voxel based male phantoms. The results show that the medical staff effective dose is highly dependent on the position of the medical staff. The results also show that the maximum medical staff effective dose in an emergency situation in the presence of a patient is ${\sim}25.5{\mu}Sv/s$.

• Nuclear Engineering and Technology
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• 제49권4호
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• pp.801-809
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• 2017

The purpose of this study is to assess the additional neutron effective dose during passive scattering proton therapy. Monte Carlo code (Monte Carlo N-Particle 6) simulation was conducted based on a precise modeling of the National Cancer Center's proton therapy facility. A three-dimensional neutron effective dose profile of the interior of the treatment room was acquired via a computer simulation of the 217.8-MeV proton beam. Measurements were taken with a $^3He$ neutron detector to support the simulation results, which were lower than the simulation results by 16% on average. The secondary photon dose was about 0.8% of the neutron dose. The dominant neutron source was deduced based on flux calculation. The secondary neutron effective dose per proton absorbed dose ranged from $4.942{\pm}0.031mSv/Gy$ at the end of the field to $0.324{\pm}0.006mSv/Gy$ at 150 cm in axial distance.

• 지구물리와물리탐사
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• 제15권4호
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• pp.227-234
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• 2012

물리검층 중에서 매질의 밀도 측정을 통해 공극률을 계산할 수 있는 밀도검층에 대한 수치 연구 결과는 국내에서는 전무하다고 해도 과언이 아니다. 이 연구에서는 MCNP (Monte Carlo N-Particle) 알고리듬에 기초하여 밀도검층을 수치모형화하고 다양한 시추공 환경이 밀도검층 결과에 미치는 영향을 분석함으로써, 밀도검층 자료해석을 위한 기틀을 마련하고자 한다. 이를 위해, MCNP 알고리듬을 이용한 밀도검층 시물레이션의 적용성을 검토하기 위해 단순한 모형에서의 검출기 반응 연구를 수행하였다. 또한 수치 실험을 위해 한국지질자원연구원에서 사용하고 있는 상용 밀도검층기(Robertson Geologging사)에 기초하여 밀도검층기를 수치모델링하였다. 다양한 밀도의 매질에서 시추공 지름을 바꿔가면서 밀도검층 시물레이션을 수행함으로써, Robertson Geologging사의 밀도검층기를 위한 교정곡선을 제시하였다. 이 교정곡선에 기초하여 매질의 밀도를 보다 정확히 분석하고 다양한 시추공환경 변화가 밀도검층에 미치는 영향을 분석하기 위해, 공내수 유무에 따른 밀도검층 반응의 변화 및 시추공 케이싱의 종류에 따른 밀도검층 반응의 변화를 수치모델링을 통해 분석하였다. 이 연구는 밀도검층 시 시추공환경 변화가 검층결과에 미치는 영향을 이해하는 것을 돕고, 향후 국내 시추공환경의 밀도검층에 대한 보다 정확한 해석을 위한 연구의 기초가 될 것으로 기대한다.

• 대한전기학회:학술대회논문집
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• 대한전기학회 1996년도 하계학술대회 논문집 C
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• pp.1932-1934
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• 1996

Electron transport coefficients are calculated in nitrogen over the E/p range $50{\sim}700\;V\;cm^{-1}$ $Torr^{-1}$ by a Monte Carlo method, using a set of electron collision cross sections measured by authors.

• 대한방사선기술학회지:방사선기술과학
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• 제45권4호
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• pp.331-339
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• 2022

The purpose of this study was to evaluate maternal organ and fetal doses by week of pregnancy for pregnant women nuclear medicine practitioners in the nuclear medicine field. In addition, we intend to present basic data for the management of exposure doses of female nuclear medicine practitioners. In this study, phantoms of childbearing women, 3, 6, 9 months pregnant women were simulated using MCNPX(Monte Carlo N-Particle Extended) among the Monte Carlo methods. First, volume source was constructed based on 10 cm of the anterior part of the lower abdomen of the phantom, and the organ and fetal doses were evaluated for each week of the pregnant woman according to the type of radioactive isotope. Second, the organ and fetal dose of pregnant women were evaluated by increasing the distance between the source and the abdominal surface by 50 and 100 cm. As a result, ¹⁸F sources showed high organ and fetal doses in pregnant women 0 to 3 months, and the dose distribution gradually decreased in 6 to 9 months pregnant women. The distribution of organ and fetal doses for ⁹⁹mTc and ¹²³I sources showed the same tendency as that of ¹⁸F, and the overall absorbed dose distribution was relatively lower than that of ¹⁸F. Through this study, it is considered that workers in the early stages of pregnancy within 3 months will need appropriate management to minimize occupational exposure dose.

• Journal of Radiation Protection and Research
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• 제41권2호
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• pp.123-131
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• 2016

Background: With the increase in the number of particle accelerator facilities under either operation or construction, the accurate calculation using Monte Carlo codes become more important in the shielding design and radiation safety evaluation of accelerator facilities. Materials and Methods: The calculations with different physics models were applied in both of cases: using only physics model and using the mix and match method of MCNPX code. The issued conditions were the interactions of 600 MeV proton and $290MeV{\cdot}n^{-1}$ oxygen with a carbon target. Both of cross-section libraries, JENDL High Energy File 2007 (JENDL/HE-2007) and LA150, were tested in this calculation. In the case of oxygen ion interactions, the calculation results using LAQGSM physics model and JENDL/HE-2007 library were compared with D. Satoh's experimental data. Other Monte Carlo calculations using PHITS and FLUKA codes were also carried out for further benchmarking study. Results and Discussion: It was clearly found that the physics models, especially intra-nuclear cascade model, gave a great effect to determine proton-induced secondary neutron spectrum in MCNPX code. The variety of physics models related to heavy ion interactions did not make big difference on the secondary particle productions. Conclusion: The variations of secondary neutron spectra and particle transports depending on various physics models in MCNPX code were studied and the result of this study can be used for the shielding design and radiation safety evaluation.

• Nuclear Engineering and Technology
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• 제48권3호
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• pp.624-634
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• 2016

Nuclear criticality safety analyses (NCSAs) considering burnup credit were performed for the GBC-32 cask. The used nuclear fuel assemblies (UNFAs) discharged from Hanbit Nuclear Power Plant Unit 3 Cycle 6 were loaded into the cask. Their axial burnup distributions and average discharge burnups were evaluated using the DeCART and Multi-purpose Analyzer for Static and Transient Effects of Reactors (MASTER) codes, and NCSAs were performed using SCALE 6.1/STandardized Analysis of Reactivity for Burnup Credit using SCALE (STARBUCS) and Monte Carlo N-Particle transport code, version 6 (MCNP 6). The axial burnup distributions were determined for 20 UNFAs with various initial enrichments and burnups, which were applied to the criticality analysis for the cask system. The UNFAs for 20- and 30-year cooling times were assumed to be stored in the cask. The criticality analyses indicated that $k_{eff}$ values for UNFAs with nonuniform axial burnup distributions were larger than those with a uniform distribution, that is, the end effects were positive but much smaller than those with the reference distribution. The axial burnup distributions for 20 UNFAs had shapes that were more symmetrical with a less steep gradient in the upper region than the reference ones of the United States Department of Energy. These differences in the axial burnup distributions resulted in a significant reduction in end effects compared with the reference.

• 지구물리와물리탐사
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• 제15권4호
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• pp.219-226
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• 2012

이 연구에서는 국내에서 연구가 미약했었던 중성자검층 수치모델링을 이용하여 다양한 시추공 환경에서의 검출기 반응을 분석하였다. 이를 위해 중성자검층 환경을 MCNP 알고리듬으로 구현하여 시뮬레이션을 수행하였다. MCNP 알고리듬은 방사선 수송 시뮬레이션이 및 3차원 기하구조 표현이 가능하여 다양한 분야에서 전세계적으로 많이 이용되고 있다. 먼저 시뮬레이션 결과를 검증하기 위해, 기존 연구의 검출기반응 결과 그래프를 이용하여 비교 분석하였다. 중성자 검층 반응 분석이 가능한 중성자 검층기의 일반적인 특징에 기초하여 수학적으로 중성자검층기 모형을 구성하여 반응을 계산하였다. 먼저, 석회암, 사암, 돌로마이트 등과 같은 매질에서 공극률을 다양하게 변화시켜 가며 수치 계산함으로써, 이 연구에서 고려하고 있는 중성자검층기의 교정곡선(calibration chart)을 도출하였다. 이에 기초하여, 실제 중성자검층 시 고려해야 할 공내수 유무에 의한 반응 변화, 염수가 중성자검층에 미치는 영향 등을 분석함으로써 시추공 환경 변화에 따라 보다 정확하게 공극률을 해석할 수 있는 기틀을 마련하고자 한다.

• Journal of Radiation Protection and Research
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• 제48권4호
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• pp.175-183
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• 2023

Background: Recently, biological adsorbents have been developed for removing radionuclides from radioactive liquid waste due to their high selectivity, eco-friendliness, and renewability. However, since they can be damaged by radiation in radioactive waste, a method for estimating the bio-adsorbent performance as a time should consider the radiation damages in terms of their renewability. This paper aims to develop a simulation method that applies a deep learning technique to rapidly and accurately estimate the adsorption performance of bio-adsorbents when inserted into liquid radioactive waste. Materials and Methods: A model that describes various interactions between a bio-adsorbent and liquid has been constructed using numerical methods to estimate the adsorption capacity of the bio-adsorbent. To generate datasets for machine learning, Monte Carlo N-Particle (MCNP) simulations were conducted while considering radioactive concentrations in the adsorbent column. Results and Discussion: Compared with the result of the conventional method, the proposed method indicates that the accuracy is in good agreement, within 0.99% and 0.06% for the R² score and mean absolute percentage error, respectively. Furthermore, the estimation speed is improved by over 30 times. Conclusion: Note that an artificial neural network can rapidly and accurately estimate the survival rate of a bio-adsorbent from radiation ionization compared with the MCNP simulation and can determine if the bio-adsorbents are reusable.

• 지질공학
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• 제27권4호
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• pp.429-438
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• 2017

지질학, 자원공학의 다양한 분야에서 적용되는 중성자검층의 활용성과 측정값의 신뢰성을 높이기 위하여 Monte Carlo 알고리듬에 기초한 MCNP 모델링을 수행하였다. 본 연구에서는 중성자 존데와 지층의 수치모형화를 기본으로 존데 고유의 교정곡선과 MCNP 모델링으로 계산한 교정곡선과의 비교를 통해 모델링의 적정성을 확인하고 암상변화, 공극 유체 특성, 시추공 지름 변화, 케이싱 영향, 공내수 영향을 모델링 결과를 이용하여 고찰하였다. 모델링 결과, 암상 변화에 따른 중성자 계수율 비율의 변화를 정량적으로 파악하였다. 시추공 지름이 존데와 비슷한 3인치의 경우, 지름이 큰 경우보다 계수율의 비가 예상보다 높게 나타났다. 이와 같은 결과는 공내수 영향이 작은 영향으로 해석되었다. 케이싱 내에서의 반응과 나공에서의 반응을 비교할 때 전반적으로 차이가 작았으며 특히 지층의 공극률이 증가하면 케이싱 영향이 감소하여 구분이 어려웠다. 지하수위 상부에 대한 모델링 결과는 지하수위 하부와는 반대의 경향을 나타냈으며 지하수위 파악에도 정성적으로 이용이 가능할 것으로 예상된다. 다양한 시추공 환경에 대한 모델링 결과는 중성자검층 현장자료의 자료처리와 해석이 유용하게 이용될 것으로 예상된다.