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Lee, Dongyoung; Kwon, K. C.; Kim, D. H.
Korea Atomic Energy Research Institute, Daejon (Korea, Republic of)2012
Korea Atomic Energy Research Institute, Daejon (Korea, Republic of)2012
AbstractAbstract
[en] Licensing technical support for NPP application of digital safety grade PLC and safety system developed in KNICS project
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Source
Feb 2012; 19 p; 3 refs, 6 figs, 3 tabs
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Report
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Oh, Inseok; Kwon, K. C.; Kim, J. Y.
Korea Atomic Energy Research Institute, Daejon (Korea, Republic of)2012
Korea Atomic Energy Research Institute, Daejon (Korea, Republic of)2012
AbstractAbstract
[en] Ο Modeling of reactor core and thermal-hydraulic using MARS code Ο Modeling of primary system and secondary system, various auxiliary system using 3KeyMaster Ο Interface development of between MARS code and 3KeyMaster for the integration of primary system and secondary system with reactor core and thermal-hydraulic Ο Development of Instructor manipulation station and display screen Ο Design and implementation of operator interface including a large display panel Ο Control panel design and building hardware
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Source
Jan 2012; 113 p; 6 refs, 22 figs, 6 tabs
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Report
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INIS IssueINIS Issue
Song, K. C.; Ko, Y. C.; Kwon, K. C.
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2012
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2012
AbstractAbstract
[en] Project of the Atomic Energy Technology Record is the project that summarizes and records whole process, from the background to the performance, of each category in all fields of nuclear science technology which have been researched and developed at KAERI. This project includes development of Data And Documents Advanced at KAERI. This project includes development of Data And Documents Advanced Management System(DADAMS) to collect, organize and preserve various records occurred in each research and development process. In addition, it means the whole records related to nuclear science technology for the past, present and future. This report summarizes research contents and results of 'Project of Atomic Energy Technology Record'. Section 2 summarizes the theoretical background, the current status of records management in KAERI and the overview of this project. And Section 3 to 6 summarize contents and results performed in this project. Section 3 is about the process of sectoral technology record, Section 4 summarizes the process of Information Strategy Master Plan(ISMP), Section 5 summarizes the development of Data And Documents Advanced Management System(DADAMS) and Section 6 summarizes the process of collecting, organizing and digitalizing of records
Primary Subject
Source
Dec 2012; 127 p; Also available from KAERI; 18 figs, 8 tabs
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Report
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Lee, Dong Young; Kwon, K. C.; Park, J. C.
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)2003
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)2003
AbstractAbstract
[en] The CNS(Compact Nuclear Simulator) has been using for the operation training and the function evaluation of the nuclear power for control system plant. The modeling code of the CNS is operating on the HP Unix Operation System(OS). As the HP Unix Operation System(OS) is upgraded, application programs developed on lower version of OS did not work well. In this project, the application program is changed to work in the upgrade version of OS, and the software obsolescence is resolved. Also GUI(Graphic User Interface) for the instructor is developed
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Source
Apr 2003; 24 p; Also available from Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); 3 refs, 14 figs
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Report
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INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] This paper describes the design progress for data management and communication networks to be co-operated as subsystems in KALIMER MMIS. Main functions and design bases are being established and validated for functional modules of these subsystems. Real-time data acquisition and signal validation, databases, and data logging have been designed as each functional module of data management while data interfaces of communication networks have been designed with the system information from Top-Tier Requirements for KALIMER MMIS. The conceptual design shall be refined through the iterative and detailed one
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Secondary Subject
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KAERI, Taejon (Korea, Republic of); [CD-ROM]; Oct 1998; [7 p.]; 1998 autumn meeting of the Korean Nuclear Society; Seoul (Korea, Republic of); 30-31 Oct 1998; Available from KNS, Taejon (KR); 9 refs, 2 figs
Record Type
Miscellaneous
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Conference
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Choi, J. G.; Kwon, K. C.; Lee, D. Y.
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2009
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2009
AbstractAbstract
[en] The majority of the I and C systems in today's NPPS are widely based on analog technology. Most of the existing I and C systems are facing obsolescence problem. The existing NPPs have difficulty in repairment and replacement for maintenance because manufacturers do not produce the analog devices and boards used in the I and C systems any more. Therefore, the existing NPPs are replacing the obsolete analog I and C systems with modern advanced digital systems. New NPPS are also adopting digital I and C systems because the economical efficiency and the usability of the systems become higher than the analog I and C systems. The digital I and C systems are based on two digital technologies. One is the micro-processor based digital system. The other is digital system based on programmable logic devices such as FPGA(Field Programmable Gate Array) In this research, we have collected and reviewed the types, structure, configuration technologies, vendors, and vulnerabilities of programmable logic devices in order to analyze the feasibility of adoption of safety-critical I and C systems based on programmable logic devices. In addition to this, we developed practical design guidelines and coding guidelines for programmable logic devices
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Aug 2009; 125 p; Also available from KAERI; 30 refs, 50 figs, 4 tabs
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Report
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AbstractAbstract
[en] This paper discusses the usability of a model checker VIS in the verification of safety software of NPP I and C systems. The software development environment exemplified in this paper is for PLC and ESF-CCS which are being developed in KNICS project. In this environment, STATEMATE is used in requirement analysis and design phases. PLC is expected to be implemented using C language and an assembly language because it has many interfaces with hardware like CPU, I/O devices, communication devices. ESF-CCS is supposed to be developed in terms of PLC programming languages which are defined in IEC 61131-3 standard. In this case, VIS proved to be very useful through the review. We are also able to expect greater usability of VIS if we further develop the techniques for code abstraction and automatic translation from code to verilog, which is the input of VIS
Primary Subject
Source
Korean Nuclear Society, Taejon (Korea, Republic of); [CD-ROM]; Oct 2002; [9 p.]; 2002 autumn meeting of the KNS; Yongpyoung (Korea, Republic of); 24-25 Oct 2002; Available from KNS, Taejon (KR); 5 refs, 1 fig
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Miscellaneous
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Conference
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Han, Jae Bok; Moon, B. S.; Kwon, K. C. and others
Korea Atomic Energy Research Institute, Taejon, (Korea, Republic of)2001
Korea Atomic Energy Research Institute, Taejon, (Korea, Republic of)2001
AbstractAbstract
[en] Unique nuclear I and C technology is associated with equipment design and fabrication techniques as well as basic design and detailed design techniques. Development of Instrumentation and Control System in Nuclear Power Plants has been prepared since July 2000, trying to acquire a unique nuclear I and C technology. Planning for the project has been performed to derive issues for localization of nuclear I and C equipments. Based on the planning, task forces for the project have been constructed. KAERI will be responsible for the tasks such as 'Development of Digital Reactor Safety System', 'Development of the Licensing Support Technology for Digital I and C', 'Development of NPP Monitoring and Operation Support Technology'.This work establishes detailed promotion plan and strategy for the project. The results of the work will be a basis of the project. Localization of nuclear I and C technology firstly requires the deduction of well established techniques that associated institutes already have. The Development of Instrumentation and Control System in Nuclear Power Plants project will stimulate the integration of the well established techniques and develop them further. The scope of this work covers the following tasks: - Establishment of the promotion strategy for the project - Establishment of the promotion strategy for the licensibility of the systems developed in the project - Establishment of the role assignment scheme among local nuclear I and C institutes - Establishment of the promotion strategy for the tasks of KAERI in the project
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Jul 2001; 65 p; 24 refs, 11 figs, 6 tabs
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Report
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Eom, H. S.; Kang, H. G.; Chang, S. C.; Park, G. Y.; Kwon, K. C.
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2007
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2007
AbstractAbstract
[en] This report propose a method that can produce quantitative reliability of safety-critical software for PSA by making use of Bayesian Belief Networks (BBN). BBN has generally been used to model the uncertain system in many research fields. The proposed method was constructed by utilizing BBN that can combine the qualitative and the quantitative evidence relevant to the reliability of safety-critical software, and then can infer a conclusion in a formal and a quantitative way. A case study was also carried out with the proposed method to assess the quality of software design specification of safety-critical software that will be embedded in reactor protection system. The V and V results of the software were used as inputs for the BBN model. The calculation results of the BBN model showed that its conclusion is mostly equivalent to those of the V and V expert for a given input data set. The method and the results of the case study will be utilized in PSA of NPP. The method also can support the V and V expert's decision making process in controlling further V and V activities
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Feb 2007; 98 p; Also available from KAERI; 7 refs, 10 figs, 3 tabs
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Report
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INIS IssueINIS Issue
AbstractAbstract
[en] This study was approached to reuse source programs for a nuclear simulator under PC with Open Source Software(OSS) and to extend its applicability. Source programs in the Compact Nuclear Simulator(CNS), which has been operated for institutional research and training in KAERI, were reused and implemented for Linux-PC environment with the aim of supporting the study. PC with 500 MHz processor and Linux 2.2.5-22 kernel were utilized for the reuse implementation and it was investigated for some applications, through the functional testing for its main functions as interfaced with compact control panels in the current CNS. Development and upgrade of small-scale simulators, establishment of process simulation for PC, and development of prototype predictive simulation, can effectively be enabled with the experience though the reuse implementation was limited to port only CNS programs for PC with Linux
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Korean Nuclear Society, Taejon (Korea, Republic of); [CD-ROM]; Oct 2000; [8 p.]; 2000 autumn meeting of the KNS; Taejon (Korea, Republic of); 26-27 Oct 2000; Available from KNS, Taejon (KR); 6 refs, 2 figs, 2 tab2
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Miscellaneous
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Conference
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