• Aerospace Engineering and Technology
• /
• v.11 no.1
• /
• pp.49-56
• /
• 2012

The flight software monitors the status of the satellite and performs attitude control and its own mission. Due to the operating environments and its uniqueness, the high level of reliability is required for the flight software. To this end, a variety of activities to meet the given requirements and improve the safety and reliability are made during the development of flight software. A variety of development environments should be provided to support execution of flight software on hardware or satellite simulator and dynamic verification of flight software through command/telemetry interface. The satellite flight software team has been developing the IVF to be applied to various satellite projects more effectively and to improve the reliability of flight software. In this paper, the design and configuration method of IVF for the effective verification of flight software is introduced.

• Proceedings of the KIEE Conference
• /
• 2005.05a
• /
• pp.185-187
• /
• 2005

The reactor protection system is the most important function for the safe operation of nuclear powerplants (NPPs) in that such system protects a nuclear reactor tore whose damage can cause an enormous disaster to the nuclear facility and the public. A digital reactor protection system (DRPS) is being developed in KAERI for use in the newly-constructed NPPs and also for replacing the existing analog-type reactor Protection systems. In this paper, an software verification and validation (V&V) activities for DRPS, which are independent of the DRPS development processes, are described according to the software development life cycle. The main activities of DRPS V&V processes are the software planning documentations, the verification of software requirements specification (SRS) and software design specification (SDS), the verification of codes, the tests of the integrated software and system. Moreover, the software safety analysis and the software configuration management are involved in the DRPS V&V processes. All of the V&V activities are described, in detail, in this paper.

• Proceedings of the KSME Conference
• /
• 2004.04a
• /
• pp.2053-2058
• /
• 2004

The pressurized light water cooled, medium power (330 MWt) SMART (System-integrated Modular Advanced ReacTor) has been under development at KAERI for a dual purpose : seawater desalination and electricity generation. The SMART design verification phase was followed to conduct various separate effects tests and comprehensive integral effect tests. The high temperature / high pressure thermal-hydraulic test facility, VISTA(Experimental Verification by Integral Simulation of Transient and Accidents) has been constructed to simulate the SMART-P (the one fifth scaled pilot plant) by KAERI. Experimental tests have been performed to investigate the thermal-hydraulic dynamic characteristics of the primary and the secondary systems. Heat transfer characteristics and natural circulation performance of the PRHRS (Passive Residual Heat Removal System) of SMART-P were also investigated using the VISTA facility. The coolant flows steadily in the natural circulation loop which is composed of the steam generator (SG) primary side, the secondary system, and the PRHRS. The heat transfers through the PRHRS heat exchanger and ECT are sufficient enough to enable the natural circulation of the coolant.

• Nuclear Engineering and Technology
• /
• v.49 no.7
• /
• pp.1537-1546
• /
• 2017

Many thermal-hydraulic tests have been conducted at the Korea Atomic Energy Research Institute for verification of the SMART (System-integrated Modular Advanced ReacTor) design, the standard design approval of which was issued by the Korean regulatory body. In this paper, the contributions of these tests to the standard design approval of SMART are discussed. First, an integral effect test facility named VISTA-ITL (Experimental Verification by Integral Simulation of Transients and Accidents-Integral Test Loop) has been utilized to assess the TASS/SMR-S (Transient and Set-point Simulation/Small and Medium) safety analysis code and confirm its conservatism, to support standard design approval, and to construct a database for the SMART design optimization. In addition, many separate effect tests have been performed. The reactor internal flow test has been conducted using the SCOP (SMART COre flow distribution and Pressure drop test) facility to evaluate the reactor internal flow and pressure distributions. An ECC (Emergency Core Coolant) performance test has been carried out using the SWAT (SMART ECC Water Asymmetric Two-phase choking test) facility to evaluate the safety injection performance and to validate the thermal-hydraulic model used in the safety analysis code. The Freon CHF (Critical Heat Flux) test has been performed using the FTHEL (Freon Thermal Hydraulic Experimental Loop) facility to construct a database from the $5{\times}5$ rod bundle Freon CHF tests and to evaluate the DNBR (Departure from Nucleate Boiling Ratio) model in the safety analysis and core design codes. These test results were used for standard design approval of SMART to verify its design bases, design tools, and analysis methodology.

• Proceedings of the KSR Conference
• /
• 2005.11a
• /
• pp.522-527
• /
• 2005

Rail network authority have to do the safety ensuring activities including the maintenance of railway facility, integrated performance verification between the facilities and related rolling stock and safety inspections, etc. When constructing the new lines or revising the conventional lines, full system commissioning should be done before the revenue service with railway operator. To develop the optimal full system commissioning model, the status of domestic and foreign railway facility and railway accidents are analysed and the problems of the safety management are derived. As one of countermeasures for the problems, the procedures and criteria for the full system commissioning are developed.

• Nuclear Engineering and Technology
• /
• v.55 no.11
• /
• pp.4125-4133
• /
• 2023

The transportation of spent nuclear fuel is an important process that involves road and sea transport from an interim storage facility to storage and final disposal sites. As spent nuclear fuel poses a significant risk, carefully evaluating its vibration and shock characteristics under normal transport conditions is essential. In this regard, full-scale multi-modal transport tests (MMTT) have been conducted domestically and internationally. In this paper, we discuss the process of developing a multi-body dynamics (MBD) model to analytically simulate conditions that cannot be considered in tests. The MBD model is based on the KORAD-21 transportation system was validated using the Korean MMTT results from 2020 to 2021. This paper summarizes the details of the development and verification of the MBD model for the KORAD-21 transportation system under normal transport test conditions. This approach can be applicable to various transportation scenarios and systems, and the results of this study will help to ensure that nuclear fuel transportation is conducted safely and effectively.

• Korean Journal of Construction Engineering and Management
• /
• v.16 no.3
• /
• pp.24-35
• /
• 2015

Aging educational facility shall be managed and maintained through integrated service perspectives, in consideration of functions of each facility to provide safe and comfortable environment, rather than temporarily fixing/repairing problems. For doing this, it is a must to firstly understand the limitation of highly biased performance-based maintenance practice, which is a most common type applied at present, and therefore to establish maintenance system that reflects the functions and characteristics of maintenance service that a facility was designed with. Therefore, the objective of this study is to find items that have an influence on service level recognition in order to fairly evaluate service functions of educational facilities, and subsequently to use these factors as ingredients of establishing a consistent and efficient maintenance system. Therefore this study proposed explanatory variables to measure influential factors for each major maintenance category. Then appropriate statistical verification was carried out on questionnaires that collected from a number of industry experts to test its fe asibility.

• Journal of Korean Society for Geospatial Information Science
• /
• v.16 no.3
• /
• pp.87-94
• /
• 2008

In this study, deals with selection of monitoring objects to handle emergency cases of multi-modal transfer stations and information required for emergency surveillance, recognition, verification, propagation, processing and situation closing. Furthermore, this article suggests integrated management scheme for the above information and methods which offer appropriate information required for situation handling decisions at each stage of situation changes. The transfer station which consists of facilities, passengers, and transportations has limitations in required monitoring information. So, for the situation recognition and handling strategy, case-based reasoning of the expert system was used to apply experience, knowledge, and past cases of situation handling experts. The article also suggests methods to control facilities which are operated at transfer stations and these methods can minimize spatial confusions and damages at the emergency situation. The real time situation information will be shared by proper facility controls to support services from external institutions.

• Journal of the Korea Institute of Military Science and Technology
• /
• v.3 no.2
• /
• pp.166-178
• /
• 2000

As the 21st century signifies an information-oriented society, the computer integration takes place in all walks of human presence. Needs for computer and network-integrated automation present new challenges in military as well as commercial facility systems engineering. Since the first intelligent building appeared in USA in 1984, it gradually became an essential capability for the building industry requirement these days. Intelligent Building System(IBS) is evolving to be very complex because there are many subsystems such as telecommunication(TC), office automation(OA), building automation(BA), security, construction environments, etc. During the planing phase of IBS development, therefore, a disciplined systems engineering must be performed to analyze stake- holder's requirements to build an optimized system while minimizing trial-and-error expenses and risks. This paper presents a conceptual design of BAS applying systems engineering methods. The contribution of this study includes the development of IBS subsystem specification for building automation subsystem, which is a part of IBS, using the methodology of requirement analysis, functional analysis, synthesis, and verification. A computer-aided systems engineering s/w, RDD-100, was used to improve the system design efficiency and to promote the product design knowledge management for reuse in later design programs.

• Journal of Korean Society of Water and Wastewater
• /
• v.35 no.1
• /
• pp.1-14
• /
• 2021

Eutrophication and algal blooms can lead to increase of taste and odor compounds and health problems by cyanobacterial toxins. To cope with these eco-social issues, Ministry of Environment in Korea has been reinforcing the effluent standards of wastewater treatment facilities. As a result, various advanced phosphorus removal processes have been adopted in each wastewater treatment plant nation-widely. However, a lot of existing advanced wastewater treatment processes have been facing the problems of expensive cost in operation and excessive sludge production caused by high dosage of coagulant. In this study, the sedimentation and dissolved air flotation (SeDAF) process integrated with sedimentation and flotation has been developed for enhanced phosphorus removal in wastewater treatment facilities. Design and operating parameters of the SeDAF process with the capacity of 100 ㎥/d were determined, and a demonstration plant has been installed and operated at I wastewater treatment facility (located in Gyeonggi-do) for the verification of field applicability. Several empirical evaluations for the SeDAF process were performed at demonstration-plant scale, and the results showed clearly that T-P and turbidity values of treated water were to satisfy the highest effluent standards below 0.2 mg/L and 2.0 NTU stably for all of operation cases.