• 한국컴퓨터정보학회논문지
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• 제24권8호
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• pp.37-43
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• 2019

The existing smart farm technology has been systematized for the mass production rather than the consumer. There are many problems such as economical aspect to apply to actual rural environment due to aging. The purpose of this study is to apply smart farm technology based on the applicability of population aged in rural areas. Due to the heat wave, the crops in general greenhouse cultivation facilities suffered from damage such as sunlight damage. To minimize such damage, adjust the temperature and humidity environment or install a light-shielding film. However, the workers in the rural areas are aging and the elderly who are farming alone have a lot of difficulties in doing so. In the case of people with weak physical strength, there is a danger that they may lead to safety accidents when carrying heavy loads. In this paper, we propose 'Smart Palm capable of automatic transportation function', applying small smart vehicles that follow workers to existing smart farms to improve and prevent these problems. It is a smart farm that performs the control functions of the existing smart greenhouse environment, installs the rail for each trough, and has a vehicle that follows the worker. The smart app can directly control the greenhouse and the vehicle remotely manually.

• 소성∙가공
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• 제30권1호
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• pp.35-42
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• 2021

Magnesium alloys are used in electronic devices such as laptops due to their lightweight features as well as vibration absorption and electromagnetic shielding properties. However, the precision of electronics is limited by the large number of small and precise ribs, the cost-effective manufacture of which requires appropriate technology. Plate forging is an efficient manufacturing process that can address these challenges. In this study, plate forging of magnesium alloys was investigated specifically for the fabrication of laptop cover. The plate forging process with back-pressure was used for near-net shape formation. Finite element analysis was used to select appropriate variables for back-pressure formation to generate ribs of various sizes and shapes without defects. The reliability of the analysis was verified to manufacture the prototype. The effect of back-pressure can be verified via fabrication of prototypes as well as structure and forming analysis based on finite element method. The process design factor of back-pressure increases formability without defects of under-filling and flow-through. Moreover, the tensile strength was maintained even after high temperature plate forging at 370 ℃, and the elongation was improved.

• Nuclear Engineering and Technology
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• 제55권3호
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• pp.1009-1014
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• 2023

Muon tomography is a useful method for monitoring special nuclear materials (SNMs) such as spent nuclear fuel inside dry cask storage. Multiple Coulomb scattering of muons can be used to provide information about the 3-dimensional structure and atomic number(Z) of the inner materials. Tomography using muons is less affected by the shielding material and less harmful to health than other measurement methods. We developed a muon detector for muon tomography, which consists of a plastic scintillator, 64 long wavelength-shifting (WLS) fibers attached to the top of the plastic scintillator, and silicon photomultipliers (SiPMs) connected to both ends of each WLS fiber. The muon detector can acquire X and Y positions simultaneously using a position determination algorithm. The design parameters of the muon detector were optimized using DETECT2000 and Geant4 simulations, and a muon detector prototype was built based on the results. Spatial resolution measurement was performed using simulations and experiments to evaluate the feasibility of the muon detector. The experimental results were in good agreement with the simulation results. The muon detector has been confirmed for use in a muon tomography system.

• Nuclear Engineering and Technology
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• 제55권6호
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• pp.1966-1973
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• 2023

Virtual reality technology has been widely used in the field of nuclear and radiation safety, dose rate computing in virtual environment is essential for optimizing radiation protection and planning the work in radioactive-controlled area. Because the CPU-based gamma dose rate computing takes up a large amount of time and computing power for voxelization of volumetric radioactive source, it is inefficient and limited in its applied scope. This study is to develop an efficient gamma dose rate computing code and apply into fast virtual simulation. To improve the computing efficiency of the point kernel algorithm in the reference (Li et al., 2020), we design a GPU-based computing framework for taking full advantage of computing power of virtual engine, propose a novel voxelization algorithm of volumetric radioactive source. According to the framework, we develop the GPPK(GPU-based point kernel gamma dose rate computing) code using GPU programming, to realize the fast dose rate computing in virtual world. The test results show that the GPPK code is play and plug for different scenarios of virtual simulation, has a better performance than CPU-based gamma dose rate computing code, especially on the voxelization of three-dimensional (3D) model. The accuracy of dose rates from the proposed method is in the acceptable range.

• 방사선산업학회지
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• 제17권2호
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• pp.191-197
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• 2023

Abstract KOMAC(Korea Multi-Purpose Accelerator Complex, KAERI) has been operating a 100 MeV proton accelerator and is going to produce ⁶⁸Ga isotope which is useful for diagnosis of cancer. So, it is necessary to develop a transport container for radio-activated targets. In this study, we carry out shielding analysis and structural analysis for the radio-activated target transport container using simulation programs. According to the Type A standard, the transport container includes an inner container and an overpack container. The main material of inner container is lead, and the shape is cylindrical with diameter of 152mm, height of 142mm and weight about 29 kg. It is planned to verify the possibility of field application through production of the transport container prototype in the future.

• 방사성폐기물학회지
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• 제22권2호
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• pp.139-144
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• 2024

Concrete structures must maintain their shielding abilities and structural integrity over extended operational periods. Despite the widespread use of dry storage systems for spent nuclear fuel, research on the properties of deteriorated concrete and their impact on structural performance remains limited. To address this significant research gap, static and dynamic material testing was conducted on concrete specimens carefully extracted from the outer wall of the High-flux Advanced Neutron Application ReactOr (HANARO), constructed approximately 30 years ago. Despite its age, the results reveal that the concrete maintains its structural integrity impressively well, with static compression tests indicating an average compressive strength exceeding the original design standards. Further dynamic property testing using advanced high-speed material test equipment supported these findings, showing the consistency of dynamic increase factors with those reported in previous studies. These results highlight the importance of monitoring and assessing concrete structures in nuclear facilities for long-term safety and reliability.

• 한국산학기술학회논문지
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• 제17권6호
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• pp.166-172
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• 2016

원자력발전소 일차 냉각계통 주요 설비의 외부면에 열차폐를 위해 설치되는 반사형 금속단열재의 내진 성능을 확인하기 위한 연구가 수행되었다. 추후 실제 내진 시험 수행을 대비하기 위해서 국내 내진시험 시설에서 시험이 가능한 시편의 크기와 무게의 한도를 고려하여 원전 원자로압력용기의 실제 동특성과 근접한 진동 특성을 가지는 축소모델을 설계하였다. 또한 축소모델의 외곽에 금속단열재를 설치한 유한요소해석 모델을 작성하였으며, 등가정적해석법 및 응답스펙트럼해석법을 통해서 국내 원전의 안전정지지진 층 응답스펙트럼을 적용하여 내진해석을 수행하였다. 보수성을 확보하기 위하여 일차 냉각계통 주요 기기들의 층 응답스펙트럼들을 포괄하는 포괄 응답스펙트럼을 작성하여 가진 데이터로서 사용하였다. 해석 결과 최대응력이 금속단열재 재질의 항복응력보다 충분히 작게 나오는 것을 확인하였고, 따라서 국산화 개발 중인 반사형 금속단열재가 안전정지지진이 발생할 경우에도 구조적 건전성을 유지할 수 있음을 해석을 통해 확인하였다. 본 연구 결과는 추후 수행할 예정으로 있는 내진시험 결과와 비교할 예정이며 이를 통하여 국산화된 금속단열재의 내진 성능을 확보할 수 있고 내진해석과 내진시험을 비교 분석하여 내진검증방법을 체계적으로 구축할 수 있을 것이다.

• 방사성폐기물학회지
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• 제5권2호
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• pp.155-169
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• 2007

월성 원자력 발전소의 TRF 시설에서 수집된 트리튬을 metal hydride 형태로 보관하고 있는 500 kCi급 트리튬 1차 저장용기를 발전소 밖의 폐기물 저장고로 안전하게 운반하기 위하여 트리튬 운반용기를 개발하였다. B형 운반용기의 기술기준을 적용하여 구조평가, 열평가, 방사선차폐평가, 격납평가 등을 수행하여 운반용기의 안전성을 분석하였다. 트리튬 운반용기는 정상운반조건 및 사고운반조건에서도 격납 경계가 손상되지 않는다고 평가되었다. 붕괴열로 인한 운반용기 내부 저장용기의 온도상승은 수치해석 결과, 원통형 모델에서는 $134.8^{\circ}C$로 나타났다. 운반사고 조건에 대한 열 평가로서 $800^{\circ}C$ 외부환경에 30분간 노출되었을 경우에는 단열재만의 열차폐를 고려하여 계산한 결과, 약 $405^{\circ}C$로 나타났으며, 내부 온도 상승은 1차 격납 경계인 1차 저장용기의 허용 온도인 $550^{\circ}C$에도 미치지 못하였다. 격납 차폐 평가에서도 사고조건인 $800^{\circ}C$의 외부 환경에 노출된 경우에서도 충분히 운반용기의 격납 성능을 유지할 수 있다고 판단되었다. 방사선에 대한 차폐 특성을 조사한 결과, 트리튬에서 발생된 ${\beta}-ray$ 선량은 1차 저장용기 외부 표면에서 0으로 계산되었다. 이상과 같이 500 kCi 급 트리튬 운반용기에 대한 안전성을 평가한 결과, 운반사고조건에서도 트리튬 운반용기는 전혀 이상이 없는 것으로 나타났다.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2001년도 춘계학술대회논문집D
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• pp.325-330
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• 2001

One of the principal components of the KSTAR (Korea Superconducting Tokamak Advanced Research) tokamak structure is the vacuum vessel, which acts as the high vacuum boundary for the plasma and also provides the structural support for internal components. Hyundai Heavy Industries Inc. has performed the engineering design of the vacuum vessel. Here the overall configuration of the KSTAR vacuum vessel was briefly described and then the design methodology and the analysis results were presented. The vacuum vessel consists of double walls, several ports, leaf spring style supports. Double walls are separated by reinforcing ribs and filled with baking/shielding water. The overall external dimensions of the main body are 3.39 m high, 1.11 m inner radius, 2.99 m outer radius, and made of SA240-316LN. The vacuum vessel was designed to be capable of achieving the base pressure of $1\times10^{-8}$ Torr, and also to be structurally capable of sustaining the vacuum pressure, the electromagnetic and thermal loads during plasma disruption and bakeout, respectively. The vacuum vessel will be baked out maximum $150^{\circ}C$ by hot pressurized water through the channels formed between double walls and the reinforcing ribs. A 3-D temperature distribution and the resulting thermal loads in the vessel were calculated during bakeout. It was found that the vacuum vessel and its supports were structurally rigid based on the thermal stress analysis. The maximum electromagnetic loads on the vacuum vessel induced by eddy and halo currents resulting from the engineering plasma radial and vertical disruption scenarios have been estimated. The stress analyses have been performed based on these electromagnetic loads and the resulting stresses at he critical locations of the vacuum vessel were within the allowable stresses.

• Journal of Radiation Protection and Research
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• 제6권1호
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• pp.34-40
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• 1981

방사선 치료를 위한 의료용 13 MeV 선형가속기를 설치 사용함에 따라 종사자에 대한 피폭방어를 비롯한 제반 설비구조의 설계가 중요하므로 저자들은 방사선 차폐벽과 시설구조를 법에 정해진 최대허용선량을 초과하지 않도록 계산하여 건축했으며 고에너지 선형가속기를 가동한 이후 실재 누출선량과 종사자의 피폭량을 측정하여 상호 검토하였다. 1) 방어벽의 계산은 NCRP #34 (1970)을 기초로 하였으며 이것이 가장 간단한 방법이고 경제적이었다. 2) 가속기 가동이후의 차폐벽으로부터 누출된 선량측정치는 계산에 의해 계획된 누출선량치의 약 $\frac{1}{5}$로 줄었으며 이는 치료환자의 수와 가장 안전한 수치를 사용했기 때문이었다. 3) 가속기에 의하여 방사선을 발생시키고 있는 동안 출입문 밖과 조종실 내에서의 누출선량율은 2-10mR/hr이었다. 4) 장시간 방사선을 발생시키거나 공기 조절장치의 성능이 약해졌을 때 치료실내의 오존냄새가 예측 의외로 심하였다.