• 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.

• Geophysics and Geophysical Exploration
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• v.17 no.3
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• pp.155-162
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• 2014

We performed MCNP modeling for density log, and examined its reliability and validity comparing the correction curves from physical borehole model. Based on the constructed numerical model, numerical modelings of density sonde in three-inch borehole were carried out under the various conditions such as the existence and type of casing or fluid, and also the stand-off between the sonde and borehole wall. These results of numerical modeling quantitatively reflect effects of casing and fluid in borehole, and moreover, demonstrate constant patterns with interval change from borehole wall. From this study, numerical modeling using MCNP shows a good applicability for well logging, and therefore, can be efficiently used for the calibration of well logging data under the various borehole conditions.

• The Journal of Engineering Geology
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• v.27 no.4
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• pp.429-438
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• 2017

Monte Carlo N-Particle (MCNP) modeling algorithm based on the Monte Carlo method was used to perform the simulation of neutron logging in order to increase the reliability and utilization of neutron logs applied in geological and resource engineering fields. To perform the simulation using MCNP, we used a realistic three-dimensional configuration of neutron sonde and formation. Validation of the modeling was confirmed by comparing the calibration curves of sonde manufacture with those calculated by MCNP modeling. After the validation, lithology effects, pore fluid effects, borehole diameter change, casing effect, and effects of borehole water level were investigated through modeling experiments. Numerical tests indicate that changes in neutron count ratio according to the lithology were quantitatively understood. In case of a borehole with a diameter of 3 inches, ratio of counting rates was higher than expected to be interpreted as borehole fluid has small effects on neutron logging. Effect of casing was also small in general, particular when porosity increases. Since modeling results above the groundwater level showed a tendency opposite to those below the groundwater level, neutron logs can be used to detect groundwater level. The modeling results simulated in this study for various borehole environments are expected to be used for data processing and interpretation of neutron log.

• Geophysics and Geophysical Exploration
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• v.15 no.4
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• pp.219-226
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• 2012

This study provides an analysis on results of neutron logging for various borehole environments through numerical simulation based on a Monte Carlo N-Particle (MCNP) code developed and maintained by Los Alamos National Laboratory. MCNP is suitable for the simulation of neutron logging since the algorithm can simulate transport of nuclear particles in three-dimensional geometry. Rather than simulating a specific tool of a particular service company between many commercial neutron tools, we have constructed a generic thermal neutron tool characterizing commercial tools. This study makes calibration chart of the neutron logging tool for materials (e.g., limestone, sandstone and dolomite) with various porosities. Further, we provides correction charts for the generic neutron logging tool to analyze responses of the tool under various borehole conditions by considering brine-filled borehole fluid and void water, and presence of borehole fluid.

• Geophysics and Geophysical Exploration
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• v.15 no.4
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• pp.227-234
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• 2012

In this study, we make simulation of density log using a Monte Carlo N-Particle (MCNP) algorithm to make an analysis on density logging under different borehole environments, since density logging is affected by various borehole conditions like borehole size, density of borehole fluid, thickness and type of casing, and so on. MCNP algorithm has been widely used for simulation of problems of nuclear particle transportation. In the simulation, we consider the specific configuration of a tool (Robertson Geologging Co. Ltd) that Korea institute of geoscience and mineral resources (KIGAM) has used. In order to measure accurate bulk density of a formation, it is essential to make a calibration and correction chart for the tool under considerations. Through numerical simulation, this study makes calibration plot of the density tool in material with several known bulk densities and with boreholes of several different diameters. In order to make correction charts for the density logging, we simulate and analyze measurements of density logging under different borehole conditions by considering borehole size, density of borehole fluid, and presence of casing.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05d
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• pp.139-146
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• 1996

도로건설시 다짐조절은 안정성과 내구성 향상에 중요한 의미를 가지며 이러한 다짐조절에 있어서 수분함량의 측정은 매우 중요하다. 이전에는 흙의 수분함량을 측정하기 위한 계기를 설계하기 위하여 주로 실험에 의한 방법을 사용하였으나 본 연구에서는 3차원 모델링이 가능한 MCNP코드$^{(1)}$ 를 이용하여 계측기 설계에 있어서 중요한 설계변수인 방사선원의 위치와 측정계기 사이의 거리 그리고 계기구성요소인 검출기의 위치, 개수, 흡수재, 감속재의 기하학적 구조 등을 계산하여 설정하였다.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.606-611
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• 1998

330MWt 출력의 신형 원자로인 SMART(System integrated Mod씰w Advanced ReacTor)가 전기 생산뿐만 아니라 해수의 담수화를 위한 에너지 공급을 위해 한국원자력연구소에 의해 개발되고 있다. SMART의 원자로 압력용기에서의 중성자 조사량을 기존의 각분할법 코드 대신에 몬데칼로 수송 코드인 MCNP-4A를 이용하여 평가하였다. MCNP-4A에 의한 몬데 칼로 모사는 각분할법에 비해 핵 단면적 자료, 선원항, 그리고 기하학적 모델링의 문제로부터 야기되는 불확실성을 감소시킬 수 있을 뿐만 아니라 초기 개념 설계 단계에서 상세 노심 출력 분포 자료에 의존하지 않고 선원항을 평가할 수 있는 장점이 있다. 본 연구에서는 원자로 압력 용기 내부의 원자로 노심 및 다른 구조물을 포함하는 전체 원자로 구조에 대하여 몬테 칼로 모사를 적용하였다. 1단계에서는 임계도 계산에 의해 선원항으로 이용되는 원자로 노심내의 열 출력 분포를 평가하고, 2단계에서는 노심내의 열 출력 분포를 고정 선원으로 이용하여 압력 용기에서의 중성자 조사량을평가하였다. 그 결과 SMART 압력용기의 중성자 조사량은 규제 요건을 만족하는 것으로 나타났다.

• Journal of the Korean Society of Radiology
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• v.16 no.5
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• pp.527-536
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• 2022

The radiation shielding characteristic of neutron shielding material has been studied as the preliminary study in order to design cosmic-ray shielding material. Specially, Soft Magnetic Material, known to be effective in EMP and radiation shielding, has been investigated to check if the material would be applicable to cosmic-ray shielding. In this work, thermal neutron shielding experiment was conducted and the Monte Carlo N-Particle(MCNP) was applied to employ skymap.dat, which is cosmic-ray data embedded in MCNP. As a result, polyethylene, borated polyethylene, and carbon nano tube, containing carbon or hydrogen, have been found to be effective in reduction of neutron flux below 20 MeV (including thermal, epithermal, evaporation). In contrast, the materials composed of iron such as SS316 and Soft Magnetic Material show a good shielding performance in the cascade energy range (above 20 MeV). Since Soft Magnetic Material is consisting of 13% of boron, it can also decrease thermal neutron flux, so it is expected that it would show a significant reduction on the entire range of neutron energy if the Soft Magnetic Material is used with hydrogen and carbon, so called low Z material.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.10a
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• pp.110-110
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• 1998

• Journal of the Korea Computer Industry Society
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• v.7 no.1
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• pp.7-14
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• 2006

In Korea, under the influence of the jurisdiction, usage of radioisotopes are limited. The limitation is $100[{\mu}Ci]$ or less. Therefore, in this study, basic data were designed, and the following data are needed in order to improve content measuring instrument which is suitable for radioisotopes limitation. Owing to the source and detector's properties, measuring instrument was designed geometrically, neutron and photon's particle transportation was analysed by using the MCNP code which is in Monte Carlo Method, also the location of source and detectors, geometrical structure of neutron absorber and moderator was designed.