• 한국항행학회논문지
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• 제19권1호
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• pp.15-21
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• 2015

WA-DGNSS는 지상에서 수신한 GNSS 신호를 관련 오차 계산 후 보정 정보를 생성하여 위성을 통해 사용자에게 보정 정보를 제공하는 시스템을 말한다. 사용자는 이 시스템을 통해 위치 정확도 향상 및 GNSS 신호에 대한 신뢰성을 보장 받는다. 또한 국제 민간항공기구(ICAO)에서는 항공기 이착륙 절차에 광역 보정시스템의 적용을 권고하고 있다. 본 논문에는 항공관련 소프트웨어 개발 절차 관련 규격문서인 RTCA DO-278의 소프트웨어 검증 프로세스를 참고하여 기 구축된 WA-DGNSS 광역 기준국 소프트웨어의 모듈 및 통합 테스트 단계를 구성하여 검증을 위한 방법론을 제시한다. 또한 제시한 방법론을 통해 기준국 소프트웨어 테스트를 통계적으로 검증하였으며 이러한 검증을 통해 기준국 소프트웨어의 기능이 적절히 수행됨이 확인되었다.

• Nuclear Engineering and Technology
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• 제51권2호
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• pp.356-368
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• 2019

This paper presents the verification and validation (V&V) of the STREAM/RAST-K 2.0 code system for a pressurized water reactor (PWR) analysis. A lattice physics code STREAM and a nodal diffusion code RAST-K 2.0 have been developed by a computational reactor physics and experiment laboratory (CORE) of Ulsan National Institute of Science and Technology (UNIST) for an accurate two-step PWR analysis. The calculation modules of each code were already verified against various benchmark problems, whereas this paper focuses on the V&V of linked code system. Three PWR type reactor cores, OPR-1000, three-loop Westinghouse reactor core, and APR-1400, are selected as V&V target plants. This code system, for verification, is compared against the conventional code systems used for the calculations in nuclear design reports (NDRs) and validated against measured plant data. Compared parameters are as follows: critical boron concentration (CBC), axial shape index (ASI), assembly-wise power distribution, burnup distribution and peaking factors. STREAM/RAST-K 2.0 shows the RMS error of critical boron concentration within 20 ppm, and the RMS error of assembly power within 1.34% for all the cycles of all reactors.

• 대한전자공학회:학술대회논문집
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• 대한전자공학회 2001년도 하계종합학술대회 논문집(2)
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• pp.117-120
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• 2001

This paper presents a HW/SW co-design environments and its validation for development of virtual component on the 32-bit RISC core which is used in the design of Information-Appliance-On-a-Chip. For the experimental environment, we developed the cycle-accurate instruction set simulator based on SE3208 RISC core of ADChips. To verify the function of RISC core at the cycle level, we implemented the verification environment by grafting this simulator on the Seamless CVE which is a commercial co-verification environment.

• 시스템엔지니어링워크숍
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• 통권1호
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• pp.27-31
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• 2003

This study is in a part of requirements validation plan for korean rubber-tired AGT system on test track. The AGT system is consisted subsystems as vehicle, signalling, communication, power distribution and infrastructure for rubber tire running on track. The subsystems will be installed and integrated on test track till next year for test and evaluation. This paper shows overview for test and evaluation in terms of system requirements and its validation classification, test track configuration, measuring system requirements and its configuration. The whole process of system integration and its validation will be controlled by means of KMS including documentation.

• Nuclear Engineering and Technology
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• 제54권9호
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• pp.3494-3515
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• 2022

This paper presents the development of a nodal diffusion code, RAST-V, and its verification and validation for VVER (vodo-vodyanoi energetichesky reactor) analysis. A VVER analytic solver has been implemented in an in-house nodal diffusion code, RAST-K. The new RAST-K version, RAST-V, uses the triangle-based polynomial expansion nodal method. The RAST-K code provides stand-alone and two-step computation modes for steady-state and transient calculations. An in-house lattice code (STREAM) with updated features for VVER analysis is also utilized in the two-step method for cross-section generation. To assess the calculation capability of the formulated analysis module, various verification and validation studies have been performed with Rostov-II, and X2 multicycles, Novovoronezh-4, and the Atomic Energy Research benchmarks. In comparing the multicycle operation, rod worth, and integrated temperature coefficients, RAST-V is found to agree with measurements with high accuracy which RMS differences of each cycle are within ±47 ppm in multicycle operations, and ±81 pcm of the rod worth of the X2 reactor. Transient calculations were also performed considering two different rod ejection scenarios. The accuracy of RAST-V was observed to be comparable to that of conventional nodal diffusion codes (DYN3D, BIPR8, and PARCS).

• Nuclear Engineering and Technology
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• 제53권2호
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• pp.455-465
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• 2021

The Molten Salt Reactor (MSR), one of the six advanced reactor types of the 4th generation nuclear energy systems, has many impressive features including economic advantages, inherent safety and nuclear non-proliferation. This paper introduces a system analysis code named TREND, which is developed and used for the steady and transient simulation of MSRs. The TREND code calculates the distributions of pressure, velocity and temperature of single-phase flows by solving the conservation equations of mass, momentum and energy, along with a fluid state equation. Heat structures coupled with the fluid dynamics model is sufficient to meet the demands of modeling MSR system-level thermal-hydraulics. The core power is based on the point reactor neutron kinetics model calculated by the typical Runge-Kutta method. An incremental PID controller is inserted to adjust the operation behaviors. The verification and validation of the TREND code have been carried out in two aspects: detailed code-to-code comparison with established thermal-hydraulic system codes such as RELAP5, and validation with the experimental data from MSRE and the CIET facility (the University of California, Berkeley's Compact Integral Effects Test facility).The results indicate that TREND can be used in analyzing the transient behaviors of MSRs and will be improved by validating with more experimental results with the support of SINAP.

• Nuclear Engineering and Technology
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• 제55권12호
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• pp.4518-4526
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• 2023

NECP-SARAX is a neutronics analysis code system for advanced reactor developed by Nuclear Engineering Computational Physics Laboratory of Xi'an Jiaotong University. In past few years, improvements have been implemented in TULIP code which is the cross-section generation module of NECP-SARAX, including the treatment of resonance interface, considering the self-shielding effect in non-resonance energy range, hyperfine group method and nuclear library with thermal scattering law. Previous studies show that NECP-SARAX has high performance in both fast and thermal spectrum system analysis. The accuracy of TULIP code in fast and thermal spectrum system analysis is demonstrated preliminarily. However, a systematic verification and validation is still necessary. In order to validate the applicability of TULIP code for full energy range, 147 fast spectrum critical experiment benchmarks and 170 thermal spectrum critical experiment benchmarks were selected from ICSBEP and used for analysis. The keff bias between TULIP code and reference value is less than 300 pcm for all fast spectrum benchmarks. And that bias keeps within 200 pcm for thermal spectrum benchmarks with neutron-moderating materials such as polyethylene, beryllium oxide, etc. The numerical results indicate that TULIP code has good performance for the analysis of fast and thermal spectrum system.

• 한국산업정보학회논문지
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• 제7권5호
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• pp.73-82
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• 2002

웹 어플리케이션의 경제적 연관성은 웹의 질적 유지 및 향상의 중요성이 매우 증가되고 있다. 더욱이 이러한 웹 어플리케이션의 개발을 위해 새로운 개념을 적용 및 사용 가능한 기술들은 매우 개선되고 세련된 기능들의 접목을 요구하고 있지만 조직과 개선을 책임지고 있는 개발자들은 자주 떠나는 실정에 있다. 그 결과로 이러한 수준 높은 요구시스템 기반의 모든 웹의 질적 보장을 위해 방법론과 툴들이 나타나게 하고 있다. 본 논문에서는 위에서 언급한 높은 수준의 요구사항에 만족하기 위해 하나의 웹 어플리케이션 모델을 소개하고 실제 웹 어플리케이션의 검증 및 확인 기술에 대한 개념과 향후 국내 웹사이트를 대상으로 한 분석 알고리즘을 제안하고 실험을 통한 결과를 제시하였다.

• 시스템엔지니어링학술지
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• 제5권2호
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• pp.11-16
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• 2009

This study introduces the verification, validation & accreditation (VV&A) process for modeling & simulation (M&S). VV&A is standard process for credibility of M&S. In several countries including USA, for weapon system of Defense Development using M&S, VV&A is necessary procedures to acquire official approving for credibility of M&S. Many countries have regular recommend practice guide (RPG) and instructive for VV&A of M&S. In this study, we focus the VV&A key concepts as Department of Defense RPG of USA and give the outline of the main VV&A concepts because we don't have any available VV&A Instructive. Also, this report documents the first significant VV&A application for a MITS(M-SAM Integrate Test System) including Verification and Validation(V&V) activity and tasks.

• 대한인간공학회지
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• 제18권3호
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• pp.153-169
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• 1999

The design of nuclear control room is advancing toward totally computer based human system interfaces (HSI). Computer based interfaces offer the opportunity to provide improved support of operator performance, but if not properly deployed, can introduce new challenges. This paper reviews the Westinghouse AP-600 Human Factors Verification and Validation Plan selected for HSI evaluation model of Korea next generation nuclear control rooms. The AP-600 HSI evaluation model addressed 15 evaluation issues considering major activity class of operator and task complexity factors. This paper also describes the test procedures experimenters should follow to evaluate the addressed issues.