• Journal of Applied Reliability
• /
• v.15 no.3
• /
• pp.170-175
• /
• 2015

Reliability demonstration tests (RDT's) are widely employed in design verification and process validation stages of industry. New mixed attribute-variable RDT plans that compromise demerits of the corresponding zero and zero or one failure plans which are common in practice are developed for the exponential distribution. The proposed mixed plans are compared with the typical RDT plans in terms of probability of acceptance and expected test termination time. A numerical example is provided to illustrate the mixed plans and a procedure to extend these plans to the Weibull distribution with known shape parameter is also presented.

• Journal of the Korea Institute of Military Science and Technology
• /
• v.13 no.6
• /
• pp.1080-1090
• /
• 2010

A study for improvement of credibility on test & evaluation result of interoperability in battle management information system which focused in C4I systems is very essential in rapid change of battle field environment. Realization of effective operation process with integration of developed IT also core factor for reducing of operational response time such as information gathering from sensor to shooter, time for commander's decision making. Therefore, by required to meet of high technical T&E, meet of complex software's user requirement, long-term system development period, system integration ability's request by various linkage of systems, it is high a M&S dependency to optimal performance, interpoerability's guarantee. Especially credibility on test & evaluation using M&S is very important. This paper will propse a VV&A applied methods using other VV&A case to improve credibility of M&S on test & evaluation.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1996.05a
• /
• pp.21-27
• /
• 1996

KAERI has recently developed the nuclear design code MASTER for the application to reactor physics analyses for pressurized water reactors. Its neutronics model solves the space-time dependent neutron diffusion equations with the advanced nodal methods. The major calculation categories of MASTER consist of microscopic depletion, steady-state and transient solution, xenon dynamics, adjoint solution and pin power and burnup reconstruction. The MASTER validation analyses, which are in progress aiming to submit the Uncertainty Topical Report to KINS in the first half of 1996, include global reactivity calculations and detailed pin-by-pin power distributions as well as in-core detector reaction rate calculations. The objective of this paper is to give an overall description of the CASMO/MASTER code system whose verification results are in details presented in the separate papers.

• Proceedings of the Korea Information Processing Society Conference
• /
• 2013.05a
• /
• pp.932-933
• /
• 2013

단순 부품부터 계통까지 기존의 아날로그 제품들이 최근 들어 펌 웨어(Firmware)와 고수준의 컴퓨터 언어로 구현된 응용 소프트웨어를 포함하는 디지털 설비로 바뀌고 있다. 따라서 어느 때 보다 소프트웨어의 확인 및 검증의 중요성이 대두되고 있으며, 이를 위해 학계뿐만 아니라 국제표준 기관에서 확인 및 검증을 위한 지침을 제시하고 있는 실정이다. 본 논문은 원자력발전소 출력을 제어하는 제어봉제어계통의 업그레이드와 관련하여 IEEE 1012 에 따라 수행된 독립 확인 및 검증 업무를 요약하고, 이를 통해 얻은 교훈을 기술한다.

• Transactions of the Korean Society of Automotive Engineers
• /
• v.20 no.3
• /
• pp.37-44
• /
• 2012

In this paper, the application of robust fuel gauge algorithm in the external environment to general fuel gauge system is proposed. The proposed fuel gauge system is composed of two modules which are Moving Average Filter (MAF) and Inclination Filter (IF). They are used to show correctly the amount of fuel in the external environment which are curve road, slope or acceleration/deceleration driving. In parallel, verification and validation processes using Software In the Loop Simulation (SILS) in personal computer and Hardware In the Loop Simulation (HILS) similar to actual vehicle environments are established. Through this research, it turned out to be possible to operation of gauge become correct of external environment.

• Proceedings of the KIEE Conference
• /
• 2007.04a
• /
• pp.143-145
• /
• 2007

The development of excitation control system (ECS) for emergency diesel generator in nuclear power plant is the replacement project of existing control system to resolve the maintenance problems caused by aging and obsolescence, The excitation control system is classified as a safety-related system. To guarantee the performance of developing excitation control system is equal to or higher than that of other systems, establishing the quality assurance scheme, doing software verification and validation activities, and planning equipment qualification. In this paper, we'd like to introduce the equipment qualification of excitation control system.

• Proceedings of the KIEE Conference
• /
• 1997.07c
• /
• pp.948-950
• /
• 1997

This paper presents a basic interposing logic program to control nuclear power plant. In this paper we select a target control loop among the whole interposing modules, develop logic algorithm and functional software to compose target control loop. After that we carry out V&V(Verification and Validation) into the developed logic program to improve quality and reliability.

• Korean Journal of Air-Conditioning and Refrigeration Engineering
• /
• v.24 no.6
• /
• pp.538-544
• /
• 2012

Analysis of thermal performance is required for the economic operation of turbine cycle of power plant. We developed corrective model of main feed water flow which is the most important parameter for the precise analysis of turbine cycle performance. Classification model for the identification of feed water flow measurement status was applied to increase the suitability of the corrective model. We used neural network and support vector machine to develop estimation model of main feed water flow with more generalization capability. The estimation model can be used practically to evaluate corrective performance of turbine cycle plant.

• Journal of the Korean Society of Safety
• /
• v.11 no.2
• /
• pp.143-149
• /
• 1996

We propose an Opto-Digital hybrid fingerprint Identification system based on the binary phase extraction joint transform correlator(BPEJTC) for validation and security yerification. It is shown that since the BPEJTC provides higher peak-to-sidelobe ratio than that of the conventional JTC and does not cause correlation peaks due to intra-class association, this system is well-adaptive to the multiple object environments. Experimental results show that this system has a good performance in the presence of multiple images and the variations of the same person.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1996.05a
• /
• pp.225-230
• /
• 1996

A three-dimensional reactor core simulation code, MASTER has been developed as a part of ADONIS which is the Korean core design package in KAERI. CASMO-3 is used as a precedent lattice code for two-group microscopic cross section and heterogeneous formfunctions. The pin power reconstruction capability of CASMO-3/MASTER was evaluated for a validation and verification Five B&W critical experiments were selected as benchmark problems. These problems included two experiments for CE-type and three for WH-type fuel assemblies. Two of them contained gadolinia rods as burnable absorber. Comparison of the calculated pin power distributions with the measured ones demonstrate that CASMO-3/MASTER can predict the pin power distribution as well as CASMO-3/SIMULATE-3.