• Proceedings of the Korean Nuclear Society Conference
• /
• 1996.05b
• /
• pp.493-498
• /
• 1996

A PC window-based computer code, CONPAS(CONtainment Performance Analysis System), has been developed to integrate the numerical, graphical and results-operation aspects of Level 2 probabilistic safety assessments (PSA) for nuclear power plants automatically. As a main logic for accident progression analysis, it employs a concept of the small containment phenomenological event tree(CPET) helpful to trace out visually individual accident progressions and of the large supporting event tree(LSET) for its detailed quantification. Compared with other existing computer codes for Level 2 PSA, the CONPAS code provides several advanced features: computational aspects including systematic uncertainty analysis, importance analysis, and sensitivity analysis, reporting aspects including tabling and graphic, and user-friend interface.

• Journal of the Korea Society of Computer and Information
• /
• v.29 no.6
• /
• pp.101-112
• /
• 2024

In this paper, we present EDF (Event Data Factory), an interactive tool designed to assist event log generation for process mining. EDF integrates various data connectors to improve its capability to assist users in connecting to diverse data sources. Our tool employs low-code/no-code technology, along with graph-based visualization, to help non-expert users understand process flow and enhance the user experience. By utilizing metadata information, EDF allows users to efficiently generate an event log containing case, activity, and timestamp attributes. Through log quality metrics, our tool enables users to assess the generated event log quality. We implement EDF under a cloud-based architecture and run a performance evaluation. Our case study and results demonstrate the usability and applicability of EDF. Finally, an observational study confirms that EDF is easy to use and beneficial, expanding small and medium-sized enterprises' (SMEs) access to process mining applications.

• Proceedings of the Korean Information Science Society Conference
• /
• 2000.10c
• /
• pp.487-489
• /
• 2000

회선분배장치를 제어관리하는 W/S의 Daemon 중에서 Event 처리를 담당하는 EvtProc Daemon의 경우를 들어 효율적인 부하 분산 알고리즘을 제안하였다. 본 논문에서는 대량의 Event 발생 시 담당 프로세스가 연속적으로 fork, exec 하지 않고 일정시간 대기함으로써 fork와 exec의 오버헤드를 줄이고 같은 Op Code의 연이은 Even 발생에 대기중인 프로세스가 이를 처리함으로써 더욱더 오버헤드를 줄일 수 있다. 그리고 Event를 처리하는 Child 생성에 있어 주 Child가 부하분산을 담당하게 함으로써 효율적이고 안정적으로 관리할 수 있는 방안을 제시하였다.

• Journal of Astronomy and Space Sciences
• /
• v.22 no.4
• /
• pp.537-558
• /
• 2005

This paper addresses the results of HAUSAT-2 radiation environment and effect analyses, including TID and SEE analyses. Trapped proton and electron, solar proton, galactic cosmic ray models were considered for HAUSAT-2 TID radiation environment analysis. TID was analyzed through total dose-depth curve and the radiation tolerance of TID for HAUSAT-2 components was verified by using DMBP method and sectoring analysis. HAUSAT-2 LET spectrum for heavy ion and proton were also analyzed for SEE investigation. SEE(SEU, SEL) analyses were accomplished for MPC860T2B microprocessor and K6X8008T2B memory. It was estimated that several SEUs may occur without SEL during the HAUSAT-2 mission life(2 years). Software Hamming Code EDAC has been implemented to detect and correct the SEU. In this study, all radiation analyses were conducted by using SPENVIS software.

• Journal of The Institute of Information and Telecommunication Facilities Engineering
• /
• v.9 no.3
• /
• pp.112-118
• /
• 2010

This paper propose G-code and G-Pedigree system that are development based on the e-Pedigree and EPC, and RFID solutions for logistics management is proposed. The proposed G-Pedigree system to include the forward logistics and reverse logistics all logistics and management systems are appropriate for the event, with security features, security and accessibility of critical data was strengthened. The proposed G-code systems and the EPC code of the existing RFID readers, tags can be applied to, the more you can manage the logistics-related information.

• THE INTERNATIONAL COMMERCE & LAW REVIEW
• /
• v.37
• /
• pp.217-250
• /
• 2008

The International Ship and Port Facility Security (ISPS) Code which was developed as the main response of the shipping sector to the miserable event of 11 September 2001 came into effect on 1 July 2004. The ISPS Code designed to detect and eliminate security threats affecting ships and port facilities used in international trade will significantly impact not only on the management and operation of the shipping industry but also on maritime law despite the fact that it is the regulatory framework of public law. It is expected that implementing the ISPS Code will contribute to reinforcement of maritime security on the one hand. However, on the other hand, more intensified security inspection and control measures of port states will also cause delay and additional costs which cause uncertainty in allocating security risk and cost between the contracting parties. Therefore, it is desire to insert new security clause dealing with main security issues or adapt existing clauses to new shipping environments to minimize disputes.

• Nuclear Engineering and Technology
• /
• v.31 no.5
• /
• pp.476-485
• /
• 1999

In order to evaluate the gravity-injection capability to maintain core cooling after a loss-of-shutdown-cooling event during shutdown operation, the plant conditions of the Yong Gwang Units 3&4 were reviewed. The six cases of possible gravity-injection paths from the refueling water tank (RWT) were identified and the thermal-hydraulic analyses were performed using the RELAP5/MOD3.2 code. The core cooling capability was significantly dependent on the gravity-injection path, the RCS opening, and the injection rate. In the cases with the pressurizer manway opening higher than the RWT water level, the coolant was held up in the pressurizer and the system pressure continued increasing after gravity-injection. The gravity injection eventually stopped due to the high system pressure and the core was uncovered. In the cases with the injection path and opening on the same leg side, the core cooling was dependent on whether the water injected from the RWT passed the core region or not. However, in the cases with the injection path and opening on the different leg side, the system was well depressurized after gravity-injection and the core boiling was successfully prevented for a long-term transient. In addition, from the sensitivity study on the gravity-injection flow rate, it was found that about 54 kg/s of injection rate was required to maintain the core cooling and the core cooling could be provided for about 10.6 hours after event with that injection rate from the RWT. Those analysis results would provide useful information to operators coping with the event.

• Nuclear Engineering and Technology
• /
• v.31 no.1
• /
• pp.68-79
• /
• 1999

The YGN Units 3&4 plant conditions during shutdown operation were reviewed to identify the possible event scenarios following the loss of shutdown cooling (SDC) event. For the five cases of typical reactor coolant system (RCS) configurations under the worst event sequence, such as unavailable secondary cooling and no RCS inventory makeup, the thermal hydraulic analyses were performed using the RELAP5/MOD3.2 code to investigate the plant behavior following the event. The thermal hydraulic analyses include the estimation of time to boil, time to core uncovery, and time to core heat up to determine the containment closure time to prevent the uncontrolled release of fission products to atmosphere. The result indicates that the containment closure is recommended to be achieved within 42 minutes after the loss of SDC for the steam generator (SG) inlet plenum manway open case or the large cold leg open case under the worst event sequence. The containment closure time is significantly dependent on the elevation and size of the opening and the SG secondary water level condition. It is also found that the containment closure needs to be initiated before the boiling time to ensure the survivability of the workers in the containment. These results will provide useful information to operators to cope with the loss of SDC event.

• Proceedings of the Korean Institute of Building Construction Conference
• /
• 2022.04a
• /
• pp.83-84
• /
• 2022

In Korea, smoke control measures through NFSC 501 are proposed to reduce human casualties caused by smoke in the event of a fire. However, as a result of investigating and analyzing domestic and foreign standards, it was found that domestic regulations do not set fire source, but simply set smoke emissions by floor area or height of smoke boundary. Foreign regulations set fire source. Therefore, it is judged that it is necessary to review whether the current domestic regulations can be applied in the event of an actual building fire. So, this paper aims to identify the differences in domestic and foreign standards through investigation and analysis of related standards for fire zone smoke control system in each country and use them as basic data to improve the performance of zone smoke control system.

• Nuclear Engineering and Technology
• /
• v.54 no.5
• /
• pp.1698-1711
• /
• 2022

A combined safety approach, which uses a best-estimate computer code and adopts conservative assumptions for safety systems availability, is developed and applied to the safety margin evaluation for the Loss of Condenser Vacuum (LOCV) of the 1000 MWe Korean Nuclear Power Plant. The Multi-dimensional Analysis of Reactor Safety-KINS standard (MARS-KS) code is selected as a best-estimate code and the PAPIRUS program is used to obtain different initial operational conditions through random sampling of control variables. During an LOCV event, fuel integrity is not threatened by the increase in Departure from Nuclear Boiling Ratio (DNBR). However, the high pressure in the primary coolant system and the secondary system might affect the system integrity. Thus, the peak pressure becomes a major safety concern. Transient analyses are performed for 124 cases of different initial conditions and the most conservative case, which results in the highest system pressure is selected. It is found the suggested methodology gives similar peak pressures when compared to those predicted from existing methodologies. The proposed approach is expected to minimize the time and efforts required to identify the conservative plant conditions in the existing conservative safety methodologies.