• Nuclear Engineering and Technology
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• 제41권7호
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• pp.945-952
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• 2009

The Three Mile Island Unit 2 (TMI-2) accident provides unique full scale data, thus providing opportunities to check the capability of codes to model overall plant behavior and to perform a spectrum of sensitivity and uncertainty calculations. As part of the TMI-2 analysis benchmark exercise sponsored by the Organization for Economic Cooperation and Development Nuclear Energy Agency (OECD NEA), several member countries are continuing to improve their system analysis codes using the TMI-2 data. The Republic of Korea joined this benchmark exercise in November 2005. Seoul National University has analyzed the TMI-2 accident as well as the currently proposed alternative scenario along with a sensitivity study using the Modular Accident Analysis Program Version 4.03 (MAAP4.03) code in collaboration with the Korea Hydro and Nuclear Power Company. Two input files are required to simulate the TMI-2 accident with MAAP4: the parameter file and an input deck. The user inputs various parameters, such as volumes or masses, for each component. The parameter file contains the information on TMI-2 relevant to the plant geometry, system performance, controls, and initial conditions used to perform these benchmark calculations. The input deck defines the operator actions and boundary conditions during the course of the accident. The TMI-2 accident analysis provided good estimates of the accident output data compared with the OECD TMI-2 standard reference. The alternative scenario has proposed the initial event as a loss of main feed water and a small break on the hot leg. Analysis is in progress along with a sensitivity study concerning the break size and elevation.

• Nuclear Engineering and Technology
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• 제52권4호
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• pp.661-673
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• 2020

The quarter-core simulation of BEAVRS Cycle 2 depletion benchmark has been conducted using the MCS/CTF coupling system. MCS/CTF is a cycle-wise Picard iteration based inner-coupling code system, which couples sub-channel T/H (thermal/hydraulic) code CTF as a T/H solver in Monte Carlo neutron transport code MCS. This coupling code system has been previously applied in the BEAVRS benchmark Cycle 1 full-core simulation. The Cycle 2 depletion has been performed with T/H feedback based on the spent fuel materials composition pre-generated by the Cycle 1 depletion simulation using refueling capability of MCS code. Meanwhile, the MCS internal one-dimension T/H solver (MCS/TH1D) has been also applied in the simulation as the reference. In this paper, an analysis of the detailed criticality boron concentration and the axially integrated assembly-wise detector signals will be presented and compared with measured data based on the real operating physical conditions. Moreover, the MCS/CTF simulated results for neutronics and T/H parameters will be also compared to MCS/TH1D to figure out their difference, which proves the practical application of MCS into the BEAVRS benchmark two-cycle depletion simulations.

• Nuclear Engineering and Technology
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• 제55권4호
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• pp.1563-1570
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• 2023

In this study, a DeCART/MIG uncertainty quantification (UQ) analysis code system with a multicorrelated cross section stochastic sampling (S.S.) module was established and verified through the UAM (Uncertainty Analysis in Modeling) and the BEAVRS (Benchmark for Evaluation And Validation of Reactor Simulations) benchmark calculations. For the S.S. calculations, a sample of 500 DeCART multigroup cross section sets for two major actinides, i.e., ²³⁵U and ²³⁸U, were generated by the MIG code and covariance data from the ENDF/B-VII.1 evaluated nuclear data library. In the three pin problems (i.e. TMI-1, PB2, and Koz-6) from the UAM benchmark, the uncertainties in k_inf by the DeCART/MIG S.S. calculations agreed very well with the sensitivity and uncertainty (S/U) perturbation results by DeCART/MUSAD and the S/U direct subtraction (S/U-DS) results by the DeCART/MIG. From these results, it was concluded that the multi-group cross section sampling module of the MIG code works correctly and accurately. In the BEAVRS whole benchmark problems, the uncertainties in the control rod bank worth, isothermal temperature coefficient, power distribution, and critical boron concentration due to cross section uncertainties were calculated by the DeCART/MIG code system. Overall, the uncertainties in these design parameters were less than the general design review criteria of a typical pressurized water reactor start-up case. This newly-developed DeCART/MIG UQ analysis code system by the S.S. method can be widely utilized as uncertainty analysis and margin estimation tools for developing and designing new advanced nuclear reactors.

• 한국시뮬레이션학회논문지
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• 제3권1호
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• pp.29-42
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• 1994

The architecture of a MIMD-type parallel computer system is specified: a simulator is developed to support design and evaluation of systems based on the architecture: and conducted with the simulator to evaluate system performance. The horizontal/vertical-bus(H/V-bus) system architecture provides an NxN array of processing elements which communicate with each other through a network of N horizontal buses and N vertical buses. The simulator, written in SLAM II and FORTRAN, is designed to provide high-resolution in simulating the IPC mechanism. Parameters provide the user with independent control of system size, PE speed and IPC mechanism speed. Results generated by the simulator include execution times, PE utilizations, queue lengths, and other data. The simulator is used to study system performance when a partial differential equation is solved by parallel Gauss-Seidel method. For comparisons, the benchmark is also executed on a single-bus system simulator that is derived from the H/V-bus system simulator. The benchmark is also solved on a single PE to obtain data for computing speedups. An extensive analysis of results is presented.

• International Journal of Contents
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• 제5권4호
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• pp.75-80
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• 2009

Recently high-speed memory array based on RAM, which is a type of solid-state drive (SSD), has been introduced to handle the input/output (I/O) bottleneck. But there are only a few performance studies on RAM based SSD storage with regard to diverse workloads. In this paper, we focus on the file system for RAM based memory array based NGS (Next Generation Storage) system which is running on Linux operating system. Then we perform benchmark tests on practical file systems including Ext3, ReiserFS, XFS. The result shows XFS significantly outperforms other file systems in tests that represent the storage and data requests typically made by enterprise applications in many aspects. The experiment is used to design the dedicated file system for NGS system. The results presented here can help enterprises improve their performance significantly.

• 한국IT서비스학회지
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• 제12권3호
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• pp.405-420
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• 2013

The purpose of this paper is to develop an evaluation model for e-government system in Korea which is one of world best practices of e-government systems. We have presented a method to perform an efficiency analysis of each e-government service which in a component of e-government system in Korea and to establish a benchmark target for each e-government service. To do this, the output-oriented DEA(Data Envelopment Analysis) CCR model was performed for the selected 12 e-government public services of Korean e-government system in this paper. As a result of DEA analysis, first the internet civil appeal support service, the employment comprehensive information service, and the company support information service were evaluated as the efficient solutions among the 12 e-government public services. Second the remaining 9 e-government public services were evaluated as the inefficient information services which should be improved in terms of their service levels. Finally the benchmark targets for the inefficient e-government services were suggested to improve those inefficient systems through DEA analysis.

• 한국정보처리학회논문지
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• 제3권5호
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• pp.1215-1228
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• 1996

벤치마크는 컴퓨터 시스템의 성능을 측정하기 위한 프로그램이며, 컴퓨터 시스템 의 성능은 사용자가 실행하는 응용 프로그램의 실행되는 속도에 의해서 결정 된다. 따라서, 컴퓨터 시스템의 성능을 정확히 측정하기 위한 벤치마크 프로그램은 사용자가 실행시키는 응용 프로그램과 동일한 동작 특성을 가져야 한다. 본 연구에 서는, Chaustone, Mchaustone, Fhsstone으로 이루어진 벤치마크 프로그램인 CMFstone을 구현 한다. CNFstone을 구현·실행한 결과, 다른 여러 벤치마크를 실행한 결과의 평균과 유사한 측정 결과를 보였다. 따라서, 컴퓨터 시스템의 성능 측정을 위해서 여러 벤치 마크를 실행할 필요 없이, CMFstpme을 실행시키는 것만으로도 다양한 성능 측정이 가능하다.

• Nuclear Engineering and Technology
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• 제32권3호
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• pp.214-226
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• 2000

In an effort to assess the performance of KAERI's coupled 3D kinetics - system T/H code, MARS/MASTER, Exercise III of the OECD main steam line break benchmark is solved. The analysis model of the reference plant, TMI-1 - a 2772 MWth B&W plant, consists of three major components: a core neutronics model involving 241$\times$28 neutronic nodes, a vessel 3D T/H model consisting of 374 hydrodynamic volumes, and a 1D system T/H model containing 157 hydrodynamic volumes. The results show that there is a significant amount of flow mixing occurring in the upper and lower plenum regions and the core power distribution evolves to a highly localized shape due to the presence of a stuck rod, as well as the asymmetric flow distribution. It is judged that MARS/MASTER properly captures these drastic 3-dimensional effects. Comparisons with other results submitted to OECD confirm the accuracy of the MARS/MASTER solution.

• Smart Structures and Systems
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• 제10권4_5호
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• pp.443-458
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• 2012

The structural health monitoring (SHM) benchmark study on optimal sensor placement problem for the instrumented Canton Tower has been launched. It follows the success of the modal identification and model updating for the Canton Tower in the previous benchmark study, and focuses on the optimal placement of vibration sensors (accelerometers) in the interest of bettering the SHM system. In this paper, the sensor placement problem for the Canton Tower and the benchmark model for this study are first detailed. Then an information entropy based sensor placement method with the purpose of damage detection is proposed and applied to the benchmark problem. The procedure that will be implemented for structural damage detection using the data obtained from the optimal sensor placement strategy is introduced and the information on structural damage is specified. The information entropy based method is applied to measure the uncertainties throughout the damage detection process with the use of the obtained data. Accordingly, a multi-objective optimal problem in terms of sensor placement is formulated. The optimal solution is determined as the one that provides equally most informative data for all objectives, and thus the data obtained is most informative for structural damage detection. To validate the effectiveness of the optimally determined sensor placement, damage detection is performed on different damage scenarios of the benchmark model using the noise-free and noise-corrupted measured information, respectively. The results show that in comparison with the existing in-service sensor deployment on the structure, the optimally determined one is capable of further enhancing the capability of damage detection.

• 한국지진공학회논문집
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• 제9권4호
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• pp.55-66
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• 2005

본 논문에서는 스마트 면진장치를 효과적으로 제어하기 위하여 퍼지관리제어기를 개발하였고 그 효율성을 검토하였다. 이를 위하여 1세대 스마트 면진 벤치마크 건물을 이용하여 수치해석을 수행하였다. 대상 벤치마크 구조물은 부정형의 평면을 가지고 있는 8층 건물이고 탄성베어링과 MR 감쇠기로 이루어진 스마트 면진장치가 설치되어 있다. 본 논문에서는 다목적 유전자 알고리즘을 이용하여 원거리 지진과 근거리 지진에 대하여 각각 면진구조물을 효과적으로 제어할 수 있는 하위 퍼지제어기를 개발한다. 최적화과정에서는 구조물의 최대 및 RMS 가속도와 면진층 변위의 저감이 목적으로 사용된다. 벤지마크 건물에 지진하중이 가해지면 두 개의 하위 퍼지제어기에서는 각각 다른 명령전압이 제공되는데 이 명령전압들은 퍼지관리제어기의 추론과정에 기반하여 실시간으로 참여율이 조절되어 하나의 명령전압으로 조합된다. 수치해석을 통하여 제안된 퍼지관리제어기법을 사용함으로써 상부구조물의 응답과 면진층의 변위를 효과적으로 줄일 수 있음을 확인할 수 있다.