• Journal of the Korean Data and Information Science Society
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• 제24권1호
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• pp.95-103
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• 2013

랜덤화 블록 모형에서 처리 간의 차이 유무를 검정하는 비모수 방법은 일반 대립가설에서는 Friedman (1937)이, 순서 대립가설에서는 Page (1963)가 제안한 검정법이 있다. 이 방법은 각 블록 내 처리 간의 순위를 이용하여 처리 간의 차이를 검정하는 검정법이다. 본 논문에서는 Hodges와 Lehmann (1962)의 정렬 방법과 Chung과 Kim (2007)이 제안한 결합위치 검정법을 확장하여 랜덤화 블록 모형에서 새로운 비모수적 방법을 제시하였다. 또한, 모의실험을 통하여 모수적 방법과 기존의 비모수적 방법과의 검정력을 비교하였다.

• Journal of the Korean Data and Information Science Society
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• 제7권2호
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• pp.235-245
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• 1996

확률변수 (X,Y)가 이변량 정규분포를 따르는 경우, 모상관계수 ${\rho}$에 관한 여러 가설들 중에서 $H_{0}:{\rho}={\rho}_{0}$인 경우에는 알려진 분포를 이용한 통계적 추론을 하기가 어렵다. 이러한 경우 Fisher에 의해 제안된 Z-변환을 이용한 근사적 검정법이 사용되어 오고 있으나 근사적인 방법이기 때문에 주어진 표본의 크기가 충분히 많지 않은 경우에는 적용에 무리가 있을 수 있다. 그래서 본 논문에서는 먼저 표본 상관계수 R의 분포를 모의실험을 통하여 직접 구하여 검정한 정확 검정법과, 붙스트랩(bootstrap) 방법을 이용하여 구한 붙스트랩 검정법을 제시하고, Fisher의 방법의 효율성과 실제성을 검토하고 제시된 방법들과 서로 비교하고자 한다.

• Communications for Statistical Applications and Methods
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• 제16권1호
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• pp.115-125
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• 2009

경영.경제분야에서 사용되는 모형 가운데 연립방정식 모형은 모형 내에서 결정되는 내생변수와 모형 외부로부터 결정된 외생변수들로 구성된 M개의 방정식과 T개의 관찰치로 이루어진 회귀방정식체계이며, 모형에 대한 모수식별 및 유일해의 존재여부에 대한 결정방법으로 순서조건과 계수조건이 있다. 그러나 대부분 연립방정식 모형이 이들 조건을 만족한다는 가정하에서 모수들을 추정하기 때문에 추정값이 비효율적이거나, 유일한 모수 추정값이 존재하지 않는 경우가 이들 조건에 따라 발생할 수 있다. 본 연구에서는 순서조건을 만족한다는 가정 하에서 계수조건의 충족여부를 검정하기 위한 검정통계량을 새롭게 제시하고 이의 근사분포를 도출하였으며, 이와 함께 모의 실험을 통하여 제안한 검정통계량의 검정력을 살펴보았다.

• Wind and Structures
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• 제19권4호
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• pp.421-441
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• 2014

With the assistance of typhoon field data at aerial elevation level observed by meteorological satellites and wind velocity and direction records nearby the ground gathered in Guangzhou Weather Station between 1985 and 2001, some key wind field parameters under typhoon climate in Guangzhou region were calibrated based on Monte-Carlo stochastic algorithm and Meng's typhoon numerical model. By using Peak Over Threshold method (POT) and Generalized Pareto Distribution (GPD), Wind field characteristics during typhoons for various return periods in several typical engineering fields were predicted, showing that some distribution rules in relation to gradient height of atmosphere boundary layer, power-law component of wind profile, gust factor and extreme wind velocity at 1-3s time interval are obviously different from corresponding items in Chinese wind load Codes. In order to evaluate the influence of typhoon field parameters on long-span flexible bridges, 1:100 reduced-scale wind field of type B terrain was reillustrated under typhoon and normal conditions utilizing passive turbulence generators in TJ-3 wind tunnel, and wind-induced performance tests of aero-elastic model of long-span Guangzhou Xinguang arch bridge were carried out as well. Furthermore, aerodynamic admittance function about lattice cross section in mid-span arch lib under the condition of higher turbulence intensity of typhoon field was identified via using high-frequency force-measured balance. Based on identified aerodynamic admittance expressions, Wind-induced stochastic vibration of Xinguang arch bridge under typhoon and normal climates was calculated and compared, considering structural geometrical non-linearity, stochastic wind attack angle effects, etc. Thus, the aerodynamic response characteristics under typhoon and normal conditions can be illustrated and checked, which are of satisfactory response results for different oncoming wind velocities with resemblance to those wind tunnel testing data under the two types of climate modes.

• Nuclear Engineering and Technology
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• 제55권12호
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• pp.4447-4464
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• 2023

This paper focuses on the development of a new computational model of the CNESTEN's TRIGA Mark II research reactor using the 3D continuous energy Monte-Carlo code TRIPOLI-4 (T4). This new model was developed to assess neutronic simulations and determine quantities of interest such as kinetic parameters of the reactor, control rods worth, power peaking factors and neutron flux distributions. This model is also a key tool used to accurately design new experiments in the TRIGA reactor, to analyze these experiments and to carry out sensitivity and uncertainty studies. The geometry and materials data, as part of the MCNP reference model, were used to build the T4 model. In this regard, the differences between the two models are mainly due to mathematical approaches of both codes. Indeed, the study presented in this article is divided into two parts: the first part deals with the development and the validation of the T4 model. The results obtained with the T4 model were compared to the existing MCNP reference model and to the experimental results from the Final Safety Analysis Report (FSAR). Different core configurations were investigated via simulations to test the computational model reliability in predicting the physical parameters of the reactor. As a fairly good agreement among the results was deduced, it seems reasonable to assume that the T4 model can accurately reproduce the MCNP calculated values. The second part of this study is devoted to the sensitivity and uncertainty (S/U) studies that were carried out to quantify the nuclear data uncertainty in the multiplication factor k_eff. For that purpose, the T4 model was used to calculate the sensitivity profiles of the k_eff to the nuclear data. The integrated-sensitivities were compared to the results obtained from the previous works that were carried out with MCNP and SCALE-6.2 simulation tools and differences of less than 5% were obtained for most of these quantities except for the C-graphite sensitivities. Moreover, the nuclear data uncertainties in the k_eff were derived using the COMAC-V2.1 covariance matrices library and the calculated sensitivities. The results have shown that the total nuclear data uncertainty in the k_eff is around 585 pcm using the COMAC-V2.1. This study also demonstrates that the contribution of zirconium isotopes to the nuclear data uncertainty in the k_eff is not negligible and should be taken into account when performing S/U analysis.

• Nuclear Engineering and Technology
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• 제48권5호
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• pp.1273-1279
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• 2016

Production of iodine-131 by neutron activation of tellurium in tellurium dioxide ($TeO_2$) material requires a target that meets the safety requirements. In a radiopharmaceutical production unit, a new lid for a can was designed, which permits tight sealing of the target by using tungsten inert gaswelding. The leakage rate of all prepared targets was assessed using a helium mass spectrometer. The accepted leakage rate is ${\leq}10^{-4}mbr.L/s$, according to the approved safety report related to iodine-131 production in the TRIGA Mark II research reactor (TRIGA: Training, Research, Isotopes, General Atomics). To confirm the resistance of the new design to the irradiation conditions in the TRIGA Mark II research reactor's central thimble, a study of heat effect on the sealed targets for 7 hours in an oven was conducted and the leakage rates were evaluated. The results show that the tightness of the targets is ensured up to $600^{\circ}C$ with the appearance of deformations on lids beyond $450^{\circ}C$. The study of heat transfer through the target was conducted by adopting a one-dimensional approximation, under consideration of the three transfer modes-convection, conduction, and radiation. The quantities of heat generated by gamma and neutron heating were calculated by a validated computational model for the neutronic simulation of the TRIGA Mark II research reactor using the Monte Carlo N-Particle transport code. Using the heat transfer equations according to the three modes of heat transfer, the thermal study of I-131 production by irradiation of the target in the central thimble showed that the temperatures of materials do not exceed the corresponding melting points. To validate this new design, several targets have been irradiated in the central thimble according to a preplanned irradiation program, going from4 hours of irradiation at a power level of 0.5MWup to 35 hours (7 h/d for 5 days a week) at 1.5MW. The results showthat the irradiated targets are tight because no iodine-131 was released in the atmosphere of the reactor building and in the reactor cooling water of the primary circuit.