• Nuclear Engineering and Technology
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• 제52권1호
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• pp.14-18
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• 2020

Korea Atomic Energy Research Institute (KAERI) has carried out various neutronics experiments in the commissioning stage of the Jordan Research and Training Reactor (JRTR), and this paper introduces the results of first criticality prediction and experiment for the JRTR. The Monte Carlo Code for Advanced Reactor Design and analysis (McCARD) with the ENDF/B-VII.0 nuclear library was used for prediction calculations in the process of the first criticality approach, which was performed to provide reference for the first criticality experiment. In the experiment, fuel loading was carried out by measuring the inverse multiplication factor (1/M) to predict the number of fuel assemblies at the first criticality, and the first critical was reached on April 25, 2016. Comparing the first criticality prediction and experiment, the calculated and measured CAR (Control Absorber Rod) heights for the first criticality were 575 mm and 570.5 mm, respectively, that is, the difference between the two results was approximately 5 mm. From this result, it was confirmed that JRTR manufacturing and various experiments had successfully progressed as designed.

• Nuclear Engineering and Technology
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• 제53권1호
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• pp.1-18
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• 2021

The criticality analysis of VVER-1000 mock-up benchmark experiments from the LR-0 research reactor operated by the Research Center Rez in the Czech Republic has been conducted with the MCS Monte Carlo code developed at the Computational Reactor Physics and Experiment laboratory of the Ulsan National Institute of Science and Technology. The main purpose of this work is to evaluate the newest ENDF/B-VIII.0 nuclear data library against the VVER-1000 mock-up integral experiments and to validate the criticality analysis capability of MCS for light water reactors with hexagonal fuel lattices. A preliminary code/code comparison between MCS and MCNP6 is first conducted to verify the suitability of MCS for the benchmark interpretation, then the validation against experimental data is performed with both ENDF/B-VII.1 and ENDF/B-VIII.0 libraries. The investigated experimental data comprises six experimental critical configurations and four experimental pin-by-pin power maps. The MCS and MCNP6 inputs used for the criticality analysis of the VVER-1000 mock-up are available as supplementary material of this article.

• Nuclear Engineering and Technology
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• 제52권6호
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• pp.1148-1155
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• 2020

This work presents two different methods for quantifying and propagating the uncertainty associated with fuel composition at end of life for cask criticality calculations. The first approach, the computational approach uses parametric uncertainty including those associated with nuclear data, fuel geometry, material composition, and plant operation to perform forward depletion on Monte-Carlo sampled inputs. These uncertainties are based on experimental and prior experience in criticality safety. The second approach, the data-driven approach relies on using radiochemcial assay data to derive code bias information. The code bias data is used to perturb the isotopic inventory in the data-driven approach. For both approaches, the uncertainty in k_eff for the cask is propagated by performing forward criticality calculations on sampled inputs using the distributions obtained from each approach. It is found that the data driven approach yielded a higher uncertainty than the computational approach by about 500 pcm. An exploration is also done to see if considering correlation between isotopes at end of life affects k_eff uncertainty, and the results demonstrate an effect of about 100 pcm.

• 한국수자원학회논문집
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• 제45권4호
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• pp.383-391
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• 2012

본 연구는 다기준 의사결정 문제에서 항상 발생하는 가중치와 대안들의 평가치에 대한 불확실성을 최소화하기 위해 민감도 분석을 수행하는 절차를 제시하였다. 제기되는 가중치에 대한 불확실성을 극복하기 위해 일반적으로 순위가 뒤바뀔 수 있는 가장 민감한 평가기준의 결정과 대안의 효과 측정자료의 결정이 있다. 본 연구는 유량확보와 수질개선을 위한 수자원 계획수립을 위해가중합계법을 이용한 문제에 두 경우의 민감도분석을 모두수행하였다. 이 과정에서 결정계수와 민감도 계수를 산정하여 이용하였다. 본 연구에서 제시한 민감도 분석 과정은 향후 수자원 계획 수립에 폭넓게 활용될 수 있다.

• 자원리싸이클링
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• 제27권3호
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• pp.66-77
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• 2018

우리나라의 희유금속 수입액은 6,034 백만불에 달하나 국내 희유금속 자급률은 1% 수준에 불과하여 효율적인 비축제도의 운영이 필요하다. 이에 본 연구에서는 효율적인 비축전략 수립을 위해 비축 대상이 되는 희유금속의 유 무형 위험 요인을 정량화하여 비축 적정성을 평가할 수 있는 체계를 수립하였다. 본 연구에서 개발한 모형은 중장기적인 관점에서 기술변화와 시장변화에 맞추어 우선 비축이 요구되는 희유금속을 선별하고 비축정책의 방향성을 제시하는데 그 목적이 있다. 모형을 통해 도출된 평가결과는 위험상태 행렬(criticality matrix)로 표현되어 희유금속의 안보수준을 정량적으로 측정할 수 있으며 상대비교를 가능케 한다. 따라서 향후 정책수립에 있어 본 논문에서 제안한 모형이 활용된다면 보다 효율적인 비축정책 수립이 가능할 것으로 기대된다.

• 한국콘텐츠학회논문지
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• 제18권9호
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• pp.125-140
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• 2018

최근 하드웨어 성능의 급속한 발전에 따라 임베디드 시스템은 기존의 단순한 기능만을 수행하던 시스템에서 다양한 기능을 수행하는 시스템으로 변모하고 있다. 이와 같이 서로 다른 중요도를 가지는 소프트웨어들로 구성된 시스템을 중요도 혼재 시스템(MCS: Mixed-Criticality System)이라고 한다. 현재 중요도 혼재 시스템 관련 프로젝트는 관련 산업이 발달한 유럽 및 미국의 주도로 발전 방향을 모색하고 기술적인 주도권을 잡기 위한 노력을 가속하고 있으나, 국내에서의 움직임은 미미한 실정이다. 그러므로 이와 관련된 기술 및 시장 주도권 선점을 위한 다양한 기반 기술의 연구 및 프로젝트의 진행이 시급하다. 본 논문에서는 중요도 혼재 시스템 관련 주요 프로젝트의 연구 및 개발 동향을 분석한다. 먼저, 본 논문에서는 중요도 혼재 시스템의 정의 및 시스템 모델에 대해서 정의한 후, 중요도 혼재 시스템을 구성하는 기반 기술을 분석한다. 뿐만 아니라, 이러한 중요도 혼재 시스템을 연구하는 각국의 프로젝트 동향을 분석한 후, 향후 연구 분야를 논의한다. 본 연구를 통해, 중요도 혼재 시스템 분야의 연구 방향성 설정을 위한 세계 각국의 연구 동향 파악이 가능하며, 군사 시스템에의 접목을 위한 기틀을 마련하고자 한다.

• Nuclear Engineering and Technology
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• 제49권1호
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• pp.1-5
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• 2017

The heavy water zero power reactor (HWZPR), which is a critical assembly with a maximum power of 100 W, can be used in different lattice pitches. The last change of core configuration was from a lattice pitch of 18-20 cm. Based on regulations, prior to the first operation of the reactor, a new core was simulated with MCNP (Monte Carlo N-Particle)-4C and WIMS (Winfrith Improved Multigroup Scheme)-CITATON codes. To investigate the criticality of this core, the effective multiplication factor ($K_{eff}$) versus heavy water level, and the critical water level were calculated. Then, for safety considerations, the reactivity worth of $D_2O$, the reactivity worth of safety and control rods, and temperature reactivity coefficients for the fuel and the moderator, were calculated. The results show that the relevant criteria in the safety analysis report were satisfied in the new core. Therefore, with the permission of the reactor safety committee, the first criticality operation was conducted, and important physical parameters were measured experimentally. The results were compared with the corresponding values in the original core.

• International Journal of Naval Architecture and Ocean Engineering
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• 제8권6호
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• pp.577-588
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• 2016

Due to the uncertainties related to the flaw assessment parameters, such as flaw size, fracture toughness, loading spectrum and so on, the probability concept is preferred over deterministic one in flaw assessment. In this study, efforts have been made to develop the reliability based flaw assessment procedure which combines the flaw assessment procedure of BS7910 and first-and second-order reliability methods (FORM/SORM). Both crack length and depth of semi-elliptical surface crack at weld toe were handled as random variable whose probability distribution was defined as Gaussian with certain means and standard deviations. Then the limit state functions from static rupture and fatigue perspective were estimated using FORM and SORM in joint probability space of crack depth and length. The validity of predicted limit state functions were checked by comparing it with those obtained by Monte Carlo simulation. It was confirmed that the developed methodology worked perfectly in predicting the limit state functions without time-consuming Monte Carlo simulation.

• Nuclear Engineering and Technology
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• 제24권3호
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• pp.319-328
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• 1992

일차원 구에서 유한요소법의 Galerkin formulation이 일차형태의 단일 에너지 중성자 수송방정식의 적분법에 적용되었다. 구분적으로 1차 혹은 2차인 Lagrange 다항식들이 선형대수 방정식들의 집합을 만들기 위해 적분법에 있는 각의존 중성자속(angular flux)에 대하여 활용되었다. 수치해석이 균질구에서의 임계문제와 비균질구에서의 scalar flux 분포에 대해서 행해졌다. 공간과 각에 대하여 연속적인 유한요소를 사용한 균질구에서의 임계문제에 대한 유한요소법의 결과들은 이론적인 해들자 비교되었다. 비균질 문제에서는 각자 공간에 대하여 불연속 유한요소를 사용하여 구한 scalar flux 분포는 ANISN code에 의한 계산결과와 잘 일치하였다.

• 한국주거학회논문집
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• 제24권1호
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• pp.11-20
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• 2013

The purpose of the study was to develop a classification of management for the qualitative improvement of the management of multi-family housing. The date were analyzed using the Excel program in terms of frequency and, criticality analysis in order to draw items stage by stage. The process of research was as follows: The first process drew classification of types using the content analysis of the documented studies. The second process examined subcategories according to classification of types via interviews of supervisors. Further, the criticality analysis between the two items was examined. Additionally, when this study surveys and analyzes the satisfactions and importance of management on the basis of the classification, it can have an effect on management by reflecting the result. In conclusion, the classification of the management of multi-family housing will make up the improvement scheme of supplement education, certification related management and management regulations on the characteristics of multi-family housing by types of houses in the future.