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시스템엔지니어링 기법을 적용한 가압중수로 노심관리 지원시스템 개발 사례
염충섭,김진일,송용만,Yeom, Choong Sub,Kim, Jin Il,Song, Young Man 한국시스템엔지니어링학회 2013 시스템엔지니어링학술지 Vol.9 No.1
Systems Engineering Approach was applied to the development of operator-support core management system based on the on-site operation experience and document of core management procedures, which is for enhancing operability and safety in PHWR (Pressurized Heavy Water Reactor) operation. The dissertation and definition of the system were given on th basis of investigating and analyzing the core management procedures. Fuel management, detector calibration, safety management, core power distribution monitoring, and integrated data management were defined as main user's requirements. From the requirements, 11 upper functional requirements were extracted by considering the on-site operation experience and investigating documents of core management procedures. Detailed requirements of the system which were produced by analyzing the upper functional requirements were identified by interviewing members who have responsibility of the core management procedures, which were written in SRS (Software Requirement Specification) document by using IEEE 830 template. The system was designed on the basis of the SRS and analysis in terms of nuclear engineering, and then tested by simulation using on-site data as a example. A model of core power monitoring related to the core management was suggested and a standard process for the core management was also suggested. And extraction, analysis, and documentation of the requirements were suggested as a case in terms of systems engineering.
진영호,박수용,송용만 한국원자력학회 2009 Nuclear Engineering and Technology Vol.41 No.1
A steam generator tube rupture (SGTR) accident, which is a partial reactor building bypass scenario, has a low probability and high consequences. SAMG has been used to manage the progression of severe accidents and the release of fission products induced by an SGTR at the Wolsong plants. Four of the six SAGs in the SAMG are used to manage the progression of a severe accident induced by an SGTR at the Wolsong plants. The results of the ISAAC code calculation have shown that the proper use the SAMG can stop a severe accident from progressing and keep the reactor building intact during a severe accident. These results confirm that the SAMG is an effective means of managing the progression of severe accidents initiated by an SGTR at the Wolsong plants.
Development of Desktop Severe Accident Training Simulator
KO-RYUH KIM,박수용,송용만,안광일 한국원자력학회 2010 Nuclear Engineering and Technology Vol.42 No.2
A severe accident training simulator that can simulate important severe accident phenomena and nuclear plant behaviors is developed. The simulator also provides several interactive control devices, which are helpful to assess results of a particular accident management behavior. A simple and direct dynamic linked library (DLL) data communication method is used for the development of the simulator. Using the DLL method, various control devices were implemented to provide an interactive control function during simulation. Finally, a training model is suggested for accident mitigation training and its performance is verified through application runs.
차량 샤시 설계를 위한 CAE 시스템 환경 구축에 관한 연구
양경덕,배대성,이형복,방원준,송용만 한국자동차공학회 1994 한국자동차공학회 춘 추계 학술대회 논문집 Vol.- No.-
A CAE(Computer Aided Engineering) system for design of the chassis of a vehicle is developed. The present commercial programs for an analysis of mechanical systems are not easy to use for bachelor level of design engineers. This paper presents environments of a developed CAE system.<br/> The developed CAE system is operated on MS Windows, using its major merits. The system can carry out kinematic, quasi-static and dynamic analysis of a vehicle suspension and chasssis synthesis of a vehicle. All data and results are stored in database, and designers can extract them from the database.<br/>
손희성(H.S.Sohn),송용만(Y.M.Song),김건상(K.S.Kim) 한국자동차공학회 1995 한국자동차공학회 춘 추계 학술대회 논문집 Vol.1995 No.11_1
In this study hard points sensitive to vehicle dynamic performance of quadra link suspension, were found by quasi-static analysis with ADAMS. It was done by changing hard points and examining the analysis results. As conclusions hard points which should be changed to improve vehicle dynamic performance were proposed.<br/>
김한철,하광순,김성중,서미로,강상호,이두용,송용만,이종성,임희정,조창석,연제원,김성일,조송원,송진호,류용호 한국원자력학회 2017 Nuclear Engineering and Technology Vol.49 No.8
In order to develop a domestic research roadmap for severe accidents, a special committee was establishedby the Korean Nuclear Society. One of the subcommittees discussed the characteristics and therelevant technical issues in the stages of fission product release and physical forms of radionucliderelease and transport. The group members developed a tree to identify fission product release phenomenaby tracing failures of individual defense-in-depth barriers and added possible countermeasuresagainst failure. For each elemental issue, they searched for technical problems by examining the phenomena,accident management actions, and regulatory aspects relevant to the mitigation features forcontainment, including mitigation strategies against containment bypass accidents. Regulatory concerns,including the source term and the acceptance criteria for radionuclide release, were also considered. They identified further research needs regarding important technical issues based on the degree of thecurrent knowledge level in Korea and in foreign countries, looking at the significance and urgency ofissues and the expected research period required to reach an advanced level of knowledge. As a result,the group identified the 12 most important and urgent issues, most of which were expected to requiremid-term and long-term research periods