• Nuclear Engineering and Technology
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• 제53권8호
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• pp.2767-2773
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• 2021

We used the GEANT4 Monte Carlo MC Toolkit to simulate carbon ion beams incident on water, tissue, and bone, taking into account nuclear fragmentation reactions. Upon increasing the energy of the primary beam, the position of the Bragg-Peak transfers to a location deeper inside the phantom. For different materials, the peak is located at a shallower depth along the beam direction and becomes sharper with increasing electron density NZ. Subsequently, the generated depth dose of the Bragg curve is then benchmarked with experimental data from GSI in Germany. The results exhibit a reasonable correlation with GSI experimental data with an accuracy of between 0.02 and 0.08 cm, thus establishing the basis to adopt MC in heavy-ion treatment planning. The Kolmogorov-Smirnov K-S test further ascertained from a statistical point of view that the simulation data matched the experimentally measured data very well. The two-dimensional isodose contours at the entrance were compared to those around the peak position and in the tail region beyond the peak, showing that bone produces more dose, in comparison to both water and tissue, due to secondary doses. In the water, the results show that the maximum energy deposited per fragment is mainly attributed to secondary carbon ions, followed by secondary boron and beryllium. Furthermore, the number of protons produced is the highest, thus making the maximum contribution to the total dose deposition in the tail region. Finally, the associated spectra of neutrons and photons were analyzed. The mean neutron energy value was found to be 16.29 MeV, and 1.03 MeV for the secondary gamma. However, the neutron dose was found to be negligible as compared to the total dose due to their longer range.

• 한국전자통신학회논문지
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• 제16권1호
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• pp.1-8
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• 2021

본 논문에서는 원자력 발전소에서 사용되는 디지털 모듈을 포함하는 캐비닛의 전자파 차폐효과를 외부 전파원과 내부 디지털 모듈의 배치 변화에 따라 분석하였다. 차폐효과를 분석하기 위해서 FEKO EM 시뮬레이션 툴을 사용하여 캐비닛과 모듈을 모델링하였으며, 캐비닛의 유무에 따른 전계값을 통해서 차폐효과 분포를 도출하였다. 차폐효과는 2.4 GHz 주파수에서 캐비닛에 대한 입사각, 편파 그리고 모듈의 간격에 따라 관찰하였다. 결과 검증을 위해 차폐효과 측정용 다이폴안테나를 설계 및 제작하고 이를 활용해 캐비닛의 차폐효과를 측정하였다. 결과에 따르면 캐비닛 구조는 입사되는 전파의 편파가 지면에 수평하고, 디지털 모듈간의 간격이 넓을 때 더 높은 차폐효과를 기대 할 수 있는 것으로 분석되었다.

• 콘크리트학회논문집
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• 제28권6호
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• pp.673-683
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• 2016

최근 전 세계적으로 발생하고 있는 각종 사고 및 테러공격 등으로 인한 폭발, 충돌, 화재 사고가 빈번하게 발생하고 있으며, 특히, 2001년 미국 세계무역센터와 펜타곤에 발생한 9.11 테러사건 이후 사회적인 안전 불감증이 더욱 고조되고 있다. 또한, 2011년 일본 후쿠시마 원전사고로 인한 원전 격납건물 손상 시 발생할 수 있는 물리적, 환경적 위험성에 대한 사회적 불안감이 날로 커짐에 따라 원전격납건물, 가스탱크 등에 널리 사용되는 프리스트레스트 콘크리트 구조물에 대한 극한하중 연구가 다양하게 진행되고 있다. 본 연구에서는 2방향 비부착 프리스트레스트 콘크리트 패널 부재의 폭발저항성능을 분석하기 위하여 $1,400{\times}1,000{\times}300mm$의 철근콘크리트(RC), 프리스트레스 텐던으로만 보강된 콘크리트(PSC), 프리스트레스 텐던과 철근으로 보강된 콘크리트(PSRC) 시편을 제작하였다. 폭발하중은 ANFO 55 lbs 의 장약량을 1.0 m 이격거리로 적용하였으며, 측정하고자 하는 데이터는 초기 압력폭발하중 뿐 아니라, 반사압력, 충격량, 중앙부의 처짐, 가속도, 철근 및 콘크리트, 텐던의 변형률을 측정하여 분석하였다. 본 연구는 향후 국내외 프리스트레스트 콘크리트에 대한 방호설계 및 폭발해석 등 관련 연구분야의 중요한 자료가 될 것이라 판단된다.

• 대한기계학회논문집B
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• 제27권10호
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• pp.1464-1471
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• 2003

In order to investigate the flows with shock wave in branch, 108$^{\circ}$ elbow and T-junction of the IRWST system of standard Korean nuclear reactor, detail time dependent behaviors of unsteady flow with shock wave, vortex and so on are obtained by numerical method using compressible three-dimensional Navier-Stokes equations. At first, the complex flow including the incident and reflected shock waves, vortex and expansion waves which are generated at the corner of T-junction is calculated by the commercial code of FLUENT6 and is compared with the experimental result to obtain the validation of numerical method. Then the flow fields in above mentioned units are analyzed by numerical method of [mite volume method. In numerical analysis, the distributions of flow properties with the moving of shock wave and the forces acting on the wall of each unit which can be used to calculate the size of supporting structure in future are calculated specially. It is found that the initial shock wave of normal type is re-established its type from an oblique one having the same strength of the initial shock wave at the 4 times hydraulic diameters of downstream from the branch point of each unit. Finally, it is turned out that the maximum force acting on the pipe wall becomes in order of the T-junction, 108$^{\circ}$ elbow and branch in magnitude, respectively.

• 한국압력기기공학회 논문집
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• 제6권1호
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• pp.37-42
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• 2010

The stay cylinder weld at the steam generator of Korean Standard Nuclear Power Plants is safety class I component and is subjected to be inspected by the volumetric examination such as ultrasonic method. As accessibility of this area is limited due to the narrow space and high radiation, the existing manual inspection method involves various difficulties. Moreover operators may be exposed to internal contamination by contaminated dust during the surface buffing process to improve the inspection reliability of this area. Recently the new automatic inspection system for stay cylinder welds has been developed. The inspection system basically consists of a driving assembly, data acquisition device and signal processing units. The driving assembly is classified by 1) the scanner for inspecting and buffing the weld, 2) pillars for guiding the scanner and 3) the base frame for loading and supporting pillars. The scanner has 4 sensor modules to inspect in 4 refracted angles and 4 incident directions. These components can be inserted into the skirt of the stay cylinder through the manway hole and assembled easily by one-touch in the skirt. Data acquisition device and signal processing units developed in previous works are also newly upgraded for better processing of data analysis and evaluation. The system has been successfully demonstrated not only in the mock-up but also in the field. In this paper, newly developed inspection system for the stay cylinder weld of the steam generator is introduced and their field applications are discussed.

• 한국압력기기공학회 논문집
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• 제9권1호
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• pp.8-14
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• 2013

Steam turbine blades and discs of nuclear power plants are one of the most highly stressed areas of turbine rotor, and periodic inspection of the blade roots is essential for monitoring integrity and preventing turbine failure. Ultrasonic technique is applied for volumetric inspection of blade root. However, the complexity of blade root geometry imposes challenges to inspection of blades and discs. Recently, phased array ultrasonic inspection technology is being applied to numerous power generation inspection applications including turbine rotor. The phased array ultrasonic technique requires customized inspection wedges which are generally necessary to generate effectively higher incident angle. But the usage of this wedge can cause access limitation for the lower stage blades of turbine because of the wedge front length. Therefore, the shear wave phased array probe which can generate high inspection angle without wedge is essentially necessary. In this study, feasibility study is conducted for the shear wave phased array ultrasonic probe application to blade and disc inspection. As results, the experimental results show that the shear wave phased array probe can detect the flaw and measure its size with reliable accuracy. Therefore if this shear wave phased array probe is applied to field inspection of blade and disc, more reliable inspection is expected for turbine having access limitation.

• 대한의용생체공학회:의공학회지
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• 제28권4호
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• pp.520-529
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• 2007

An efficient method for implementing image reconstruction algorithms for Compton cameras is presented. Since Compton scattering formula establishes a cone surface from which the incident photon must have originated, it is crucial to implement a computationally efficient cone-surface integration method for image reconstruction. In this paper we assume that a cone is made up of a series of ellipses (or circles) stacked up one on top of the other. In order to reduce computational burden for tracing ellipses formed by the intersection of a cone and an image plane, we propose a new method using a series of imaginary planes perpendicular to the cone axis so that each plane contains a circle, not an ellipse. In this case the cone surface integral can be performed by simply accumulating the circles along the cone axis. To reduce the computational cost of tracing circles, only one of the circles in the cone is traced and the rest are determined by using simple trigonometric ratios. For our experiments, we used the three different schemes for tracing ellipses; (i) using the samples generated by the ellipse equation, (ii) using the fixed number of samples along a circle on the imaginary plane, and (iii) using the fixed sampling interval along a circle on the imaginary plane. We then compared performance of the above three methods by applying them to the two reconstruction algorithms - the simple back-projection method and the expectation-maximization algorithm. The experimental results demonstrate that our proposed methods (ii) and (iii) using imaginary planes significantly improve reconstruction accuracy as well as computational efficiency.

• 한국지진공학회논문집
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• 제12권6호
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• pp.55-63
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• 2008

본 연구에서는 지반-구조물 상호작용을 고려한3차원 지반-구조계의 지진응답 해석을 수행하고 그 기법의 적용성과 타당성을 검토한다. 이를 위해 구조물과 구조물 주변의 근역지반을3차원 유한요소로서 모델링하고 원역지반에 대해서는 기 개발한 3차원 동적 무한요소를 적용한다. 모든 입사 성분P, SV 그리고 SH파가 고려되었을 때, 등가 지진하중은 무한요소에 의해 구해진 무한 지반의 동적 강성과 자유장 해석을 통해 구해진 지반의 응력과 변위응답을 이용하여 구해진다. 검증 및 적용 예제는 적층 자유장의 지반응답해석과 전형적 원자로 격납건물의 지반-구조물 상호작용을 고려한 층응답 스펙트럼을 구하는 것으로 하였다. 해석 결과는 다른 기법에 의해 구해진 값들과 비교하였으며, 본 기법의 정확성과 정밀성을 확인할 수 있다.

• Nuclear Engineering and Technology
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• 제30권5호
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• pp.403-415
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• 1998

The CANDU 6 reactor assembly consists of an array of 380 pressure tubes, which are installed horizontally in a large cylindrical vessel, the Calandria, containing the low pressure heavy water moderator. The pressure tube is located inside the calandria tube and the annulus between these tubes, which forms a closed loop with $CO_2$ gas recirculating, is called the Annulus Gas System(AGS). It is designed to give an alarm to the operator even for a small pressure tube leak by a very sensitive dew point meter so that he can take a preventive action for the pressure tube rupture incident. To judge whether the operator action time is enough or not in the design of Wolsong 2,3 & 4, the Leak Before Break(LBB) assessment is required for the analysis of the pressure tube failure accident. In order to provide the required data for the LBB assessment of Wolsong Units 2, 3, 4, a series of leak detection capability tests was performed by injecting controlled rates of heavy water vapour. The data of increased dew point and rates of rise were measured to determine the alarm set point for the dew point rate of rise of Wolsong Unit 2. It was found that the response of the dew point depends on the moisture injection rate, $CO_2$ gas flow rate and the leak location. The test showed that CANDU 6 AGS can detect the very small leaks less than few g/hr and dew point rate of rise alarm can be the most reliable alarm signal to warn the operator. Considering the present results, the first response time of dew point to the AGS $CO_2$ flow rate is approximated.

• 한국지진공학회논문집
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• 제19권1호
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• pp.37-43
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• 2015

This paper presents a detailed procedure for a nonlinear soil-structure interaction of a seismically isolated NPP(Nuclear Power Plant) structure using the boundary reaction method (BRM). The BRM offers a two-step method as follows: (1) the calculation of boundary reaction forces in the frequency domain on an interface of linear and nonlinear regions, (2) solving the wave radiation problem subjected to the boundary reaction forces in the time domain. For the purpose of calculating the boundary reaction forces at the base of the isolator, the KIESSI-3D program is employed in this study to solve soil-foundation interaction problem subjected to vertically incident seismic waves. Wave radiation analysis is also employed, in which the nonlinear structure and the linear soil region are modeled by finite elements and energy absorbing elements on the outer model boundary using a general purpose nonlinear FE program. In this study, the MIDAS/Civil program is employed for modeling the wave radiation problem. In order to absorb the outgoing elastic waves to the unbounded soil region, spring and viscous-damper elements are used at the outer FE boundary. The BRM technique utilizing KIESSI-3D and MIDAS/Civil programs is verified using a linear soil-structure analysis problem. Finally the method is applied to nonlinear seismic analysis of a base-isolated NPP structure. The results show that BRM can effectively be applied to nonlinear soil-structure interaction problems.