• 항공우주정책ㆍ법학회지
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• 제32권2호
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• pp.219-246
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• 2017

핵문제는 국제레짐(resime)의 지구화를 보여주는 좋은 예이다. 1945년 8월 일본에 최초로 핵폭탄이 투하되면서 핵무기가 인류를 절멸시킬 수 있다는 역사를 통해 평화에 대한 갈망은 더욱 절실해졌다. 자국의 안보를 위한 군비증강은 국제사회에서 자존의 문제이지만, UN헌장의 목적이기도 한 국제평화와 안전을 유지하기 위해 군축 또는 군비통제는 전 인류의 평화 실현과 직결된 가장 중요한 과제일 것이다. 오늘날 군축은 국제분쟁의 평화적 해결, 집단안전보장제도와 함께 국제평화와 안전을 유지 촉진하는 중요한 수단이다. 완전한 군축 실현이 항구적인 인류의 과제일 수는 있으나, NPT 서문에서 일반적이고 완전한 군축이 표현된 것처럼 국제사회는 완전 군축을 위한 노력을 천명하고 있다. 따라서 핵문제에 대한 국제레짐과 북한의 핵문제에 대한 주요 경과를 살펴봄으로써 핵문제의 지구화 현상을 소개하고, 핵 군축을 위한 국제사회의 노력을'인류의 공동유산'개념과 우주공간 평화이용위원회 및 핵무기의 통제를 중심으로 검토한 후, 대한민국과 국제법에 직결된 사안인 북한의 핵문제를 우주법 내지 군축법적인 관점에서 평가해 보고자 한다. 또한 북한의 핵문제를 위해서는 비확산 반확산정책과 함께 집단안전보장제도가 지속적으로 강조 시도되어야 할 것이다.

• Journal of Radiation Protection and Research
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• 제25권3호
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• pp.133-135
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• 2000

• 전산구조공학
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• 제6권4호
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• pp.89-98
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• 1993

최근 원자력의 사용이 증가함에 따라 핵폐기물을 효과적으로 처리하는 문제에 관심이 집중되고 있다. 이러한 핵폐기물을 지층내에 저장할 경우 고온의 열에 의해 핵폐기물 구조체에 지대한 영향을 미치므로 지반의 열력학적 거동을 분석할 필요성이 요구된다. 본 연구는 지반내에 처분된 고온의 사용후 핵연료에 의한 열역학적인 응력이 집중되어 비선형 거동이 예상되는 저장구조체 주변에는 비선형 유한요소를 적용하고 선형거동이 예상되는 무한영역에는 선형경계요소를 사용하여, 일반적인 역학적 계와 동일한 방법으로 비선형 유한요소와 경계요소를 조합한 프로그램을 개발하였다. 사용후 핵연료 폐기구조체와 같이 국부적인 비선형거동이 예상되는 구조물에서는 조합방법이 전 영역을 비선형 유한요소로 모형화하여 해석하는 것보다 효율적임을 알 수 있었다. 또한, 지층내 지반에 영향 미치는 주요 지반계수를 변화시킨 경우, 터널경계의 변위에 이러한 계수들이 어떠한 영향을 미치는가를 개발된 방법을 사용하여 검토하였다. 검토결과, 다른 계수들의 변화보다 열팽창계수의 변화가 터널주위의 변위에 상당한 영향을 미침을 알 수 있었다.

• Nuclear Engineering and Technology
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• 제38권2호
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• pp.147-154
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• 2006

Thermal fatigue of the coolant circuits of PWR plants is a major issue for nuclear safety. The problem is especially accute in mixing zones, like T-junctions, where large differences in water temperature between the two inlets and high levels of turbulence can lead to large temperature fluctuations at the wall. Until recently, studies on the matter had been tackled at EDF using steady methods: the fluid flow was solved with a CFD code using an averaged turbulence model, which led to the knowledge of the mean temperature and temperature variance at each point of the wall. But, being based on averaged quantities, this method could not reproduce the unsteady and 3D effects of the problem, like phase lag in temperature oscillations between two points, which can generate important stresses. Benefiting from advances in computer power and turbulence modelling, a new methodology is now applied, that allows to take these effects into account. The CFD tool Code_Saturne, developped at EDF, is used to solve the fluid flow using an unsteady L.E.S. approach. It is coupled with the thermal code Syrthes, which propagates the temperature fluctuations into the wall thickness. The instantaneous temperature field inside the wall can then be extracted and used for structure mechanics computations (mainly with EDF thermomechanics tool Code_Aster). The purpose of this paper is to present the application of this methodology to the simulation of a straight T-junction mock-up, similar to the Residual Heat Remover (RHR) junction found in N4 type PWR nuclear plants, and designed to study thermal striping and cracks propagation. The results are generally in good agreement with the measurements; yet, in certain areas of the flow, progress is still needed in L.E.S. modelling and in the treatment of instantaneous heat transfer at the wall.

• 방사선산업학회지
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• 제9권3호
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• pp.143-151
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• 2015

A PET-MR system is particularly useful in diagnosing brain diseases. We have developed a prototype positron emission tomography (PET) system which can be inserted into the bore of a whole-body magnetic resonance imaging (MRI) system that enables us to obtain PET and MRI images simultaneously with a reduced cost. Silicon photomultipliers (SiPM) are appropriated as a PET detector at PET/MR system because detectors have a high gain and are insensitive to magnetic fields. Despite of its improved performance compared to that of PMT-based detectors, there is a problem of the photo-peak channel shift which is due to the increase of the temperature inside the ring detector. This problem will occur decreasing sensitivity of the PET and image distortion. In this paper, I quantitative analyze parameters of the KAIST SiPM depending on temperature by experiments. And I designed cooling methods in consideration of the degradation of sensors for correction of the temperature in the PET gantry. According to this research, we expect that distortive images and degradation of the sensitivity will not be occurred with using the above idea to reduce heat even if the PET system operates for a long time.

• Nuclear Engineering and Technology
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• 제48권1호
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• pp.144-152
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• 2016

Human capabilities, such as technical/nontechnical skills, have begun to be recognized as crucial factors for nuclear safety. One of the most common ways to improve human capabilities in general is training. The nuclear industry has constantly developed and used training as a tool to increase plant efficiency and safety. An integrated training framework was suggested for one of those efforts, especially during simulation training sessions of nuclear power plant operation teams. The developed training evaluation methods are based on measuring the levels of situation awareness of teams in terms of the level of shared confidence and consensus as well as the accuracy of team situation awareness. Verification of the developed methods was conducted by analyzing the training data of real nuclear power plant operation teams. The teams that achieved higher level of shared confidence showed better performance in solving problem situations when coupled with high consensus index values. The accuracy of nuclear power plant operation teams' situation awareness was approximately the same or showed a similar trend as that of senior reactor operators' situation awareness calculated by a situation awareness accuracy index (SAAI). Teams that had higher SAAI values performed better and faster than those that had lower SAAI values.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2001년도 하계학술대회 논문집 D
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• pp.2723-2725
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• 2001

Nuclear power generations have been developed gradually since 1950. Nowadays, 440 nuclear power generations are taking charge of 16% of electric power production in the world. The most important factor to operate the nuclear power generations is safety. It is not easy way to control nuclear power generations with safety because nuclear power generations are very complicated systems. In the main control room of the nuclear power generations, about 4000 numbers of alarms and monitoring devices are equipped to handle the signals corresponding to operating equipments. Thus, operators have to deal with massive information and to grasp the situation immediately. If they could not achieve these task, then they should make big problem in the power generations Owing to too many variables, operators could be also in the uncontrolled situation. So in this paper, automatic systems to diagnose the fault are constructed using 2 steps neural networks. This diagnosis method is based on the pattern of the principal variables which could represent the type and severity of faults.

• Nuclear Engineering and Technology
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• 제50권3호
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• pp.340-355
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• 2018

The methods and performance of a fast reactor multigroup cross section (XS) generation code EXUS-F are described that is capable of directly processing Evaluated Nuclear Data File format nuclear data files. RECONR of NJOY is used to generate pointwise XS data, and Doppler broadening is incorporated by the Gauss-Hermite quadrature method. The self-shielding effect is incorporated in the ultrafine group XSs in the resolved and unresolved resonance ranges. Functions to generate scattering transfer matrices and fission spectrum matrices are realized. The extended transport approximation is used in zero-dimensional calculations, whereas the collision probability method and the method of characteristics are used for one-dimensional cylindrical geometry and two-dimensional hexagonal geometry problems, respectively. Verification calculations are performed first for various homogeneous mixtures and cylindrical problems. It is confirmed that the spectrum calculations and the corresponding multigroup XS generations are performed adequately in that the reactivity errors are less than 50 pcm with the McCARD Monte Carlo solutions. The nTRACER core calculations are performed with the EXUS-F-generated 47 group XSs for the two-dimensional Advanced Burner Reactor 1000 benchmark problem. The reactivity error of 160 pcm and the root mean square error of the pin powers of 0.7% indicate that EXUF-F generates properly the broad-group XSs.

• 대한설비공학회:학술대회논문집
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• 대한설비공학회 2006년도 하계학술발표대회 논문집
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• pp.596-601
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• 2006

Because of insufficiency of energy resources and pollution of environment, it is necessary to develop alternative energy sources. Nuclear fission energy is used widely for source of electric Power but being restricted due to radioactivity problem. Nuclear fission is highlighted as the new generation of nuclear energy and researched worldwide because of low risk of radiation effect. The representatives of fusion research is China's EAST, KSTAR of Korea and ITER of world. Korea Superconducting Tokamak Advanced Research(KSTAR) project is on progress for the completion in August, 2007. In this study, the research of utility system for KSTAR be carried out. The utility system of KSTAR is consist of water cooling & heating system, $N_2$ gas system, DI water system, service water system and instrument air & auto control system. The progress of KSTAR utility system is under commissioning state after construction completion. The optimal operation scenario will be verified during commissioning and adopted to the KSTAR operation.

• Nuclear Engineering and Technology
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• 제52권5호
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• pp.956-963
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• 2020

Dose optimization for Radioactive Occupational Personal (ROP) is an important subject in nuclear and radiation safety field. The geometric environment of a nuclear facility is complex and the work area is radioactive, so traditional navigation model and radioactive data field cannot form an effective environment model for dose assessment and dose optimization. The environment model directly affects dose assessment and indirectly affects dose optimization, this is an urgent problem needed to be solved. Therefore, this paper focuses on an environment model used for Dose Assessment and Dose Optimization (DA&DO). We designed a multi-layer radiation field coupling modeling method, and then explored the influence of the environment model to DA&DO by virtual simulation. Then, a simulation test is done, the multi-layer radiation field coupling model for nuclear facilities is demonstrated to be effective for dose assessment and dose optimization through the experiments and analysis.