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AbstractAbstract
[en] In this paper, the expected conceptual design issues for the reactor vessel of the Sodium-Cooled Fast Reactor (SFR) are investigated and discussed with relevant structural analyses
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Korean Nuclear Society, Daejeon (Korea, Republic of); [1 CD-ROM]; Oct 2010; [2 p.]; 2010 autumn meeting of the KNS; Jeju (Korea, Republic of); 21-22 Oct 2010; Available from KNS, Daejeon (KR); 3 refs, 5 figs
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AbstractAbstract
[en] A facility for generation and application of fast neutron was developed. This facility will be used for the education of undergraduate student with a major in nuclear engineering and for collaborated researches required thermal or fast neutron irradiation. We introduce the facility for generation and application of fast neutron to researchers interested about the neutron irradiation and application in this paper
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Source
Korean Nuclear Society, Daejeon (Korea, Republic of); [1 CD-ROM]; Oct 2010; [2 p.]; 2010 autumn meeting of the KNS; Jeju (Korea, Republic of); 21-22 Oct 2010; Available from KNS, Daejeon (KR); 6 refs, 3 figs
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AbstractAbstract
[en] The characteristics of 50 Hz RCP are evaluated for the thermal margin during RCP Coastdown. To have a better knowledge of the RCP characteristics, a sensitivity study for parameters such as the homologous curve, RCP speed, RCP head and RCP inertia has been performed using a computer code, COAST. The effect of each parameter is described herein, and the simulation results are shown to evaluate RCP parameters
Primary Subject
Source
Korean Nuclear Society, Daejeon (Korea, Republic of); [1 CD-ROM]; Oct 2010; [2 p.]; 2010 autumn meeting of the KNS; Jeju (Korea, Republic of); 21-22 Oct 2010; Available from KNS, Daejeon (KR); 1 ref, 5 figs
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AbstractAbstract
[en] For the seismic evaluation of nuclear facilities, the seismic margin assessment (SMA) and the seismic probabilistic safety assessment (SPSA) have been widely used. The system level HCLPF is the criterion in the SMA methodology developed by NRC. The estimation of the system fragility is necessary in the procedure of the SPSA. Therefore, the modeling of a system fragility curve is important in these two methods. In this research, the estimation of system fragility by using composite standard deviation was studied
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Source
Korean Nuclear Society, Daejeon (Korea, Republic of); [1 CD-ROM]; Oct 2010; [2 p.]; 2010 autumn meeting of the KNS; Jeju (Korea, Republic of); 21-22 Oct 2010; Available from KNS, Daejeon (KR); 3 refs, 4 figs
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AbstractAbstract
[en] The present study is aiming at the visualization of the boiling structures for various pool boiling and flow boiling conditions by applying multiple visualization techniques simultaneously. The bubble growth rate and microlayer behavior were simultaneously visualized for an isolated boiling regime of a water by using a shadow graph and a total reflection technique, respectively
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Source
Korean Nuclear Society, Daejeon (Korea, Republic of); [1 CD-ROM]; Oct 2010; [2 p.]; 2010 autumn meeting of the KNS; Jeju (Korea, Republic of); 21-22 Oct 2010; Available from KNS, Daejeon (KR); 1 refs, 4 figs
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Park, Ho Joon; Kim, Hyun Sook; Kim, Hyun Jo; Ko, Han Suk; Lee, Byung Doo
Proceedings of the KNS autumn meeting2010
Proceedings of the KNS autumn meeting2010
AbstractAbstract
[en] Nuclear material accountancy within the framework of IAEA safeguards begins with the nuclear material accounting activities by facility operators and the State system of accounting for and control of nuclear material(SSAC), implemented in accordance with the provisions of the safeguards agreement between the IAEA and the State. IAEA verify the correctness of the nuclear material accounting information in the facility records and the reports provided by the SSAC to the IAEA. This paper are described the status of KAERI nuclear material accountancy
Primary Subject
Source
Korean Nuclear Society, Daejeon (Korea, Republic of); [1 CD-ROM]; Oct 2010; [2 p.]; 2010 autumn meeting of the KNS; Jeju (Korea, Republic of); 21-22 Oct 2010; Available from KNS, Daejeon (KR); 2 refs, 2 tabs
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AbstractAbstract
[en] MPC is applied to the steam generator feedwater and level control system. Two MPC controllers are designed. First, the MPC controller of the feedwater station is determined. Then another MPC controller for the level control is designed. The constraints arising from actual operation are taken into account. And through the simulation it is found that the designed MPC controllers give a good dynamic performance
Primary Subject
Source
Korean Nuclear Society, Daejeon (Korea, Republic of); [1 CD-ROM]; Oct 2010; [2 p.]; 2010 autumn meeting of the KNS; Jeju (Korea, Republic of); 21-22 Oct 2010; Available from KNS, Daejeon (KR); 4 refs, 3 figs
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AbstractAbstract
[en] Daylighting is the efficient use of natural light in order to minimize the need for artificial light in buildings. A well thought out building designed with daylighting can have a number of significant benefits for building owners and occupants. Increasing levels of daylight within rooms can reduce electrical lighting loads by up to 70% in some cases. In this study, the daylighting system using mini dish and optical fiber was analyzed for application to the schoolroom by the simulation of ECOTECT and RADIANCE
Primary Subject
Source
Korean Nuclear Society, Daejeon (Korea, Republic of); [1 CD-ROM]; Oct 2010; [2 p.]; 2010 autumn meeting of the KNS; Jeju (Korea, Republic of); 21-22 Oct 2010; Available from KNS, Daejeon (KR); 7 refs, 7 figs
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Chun, Chong Kuk; Nahm, Kee Yil; Lim, Jong Seon; Park, Shane
Proceedings of the KNS autumn meeting2010
Proceedings of the KNS autumn meeting2010
AbstractAbstract
[en] KEPCO NF has developed the core thermal hydraulic design code, THALES (Thermal Hydraulic AnaLyzer for Enhanced Simulation of core). This paper presents the derivation and characteristics of pressure matrix for three dimensional geometry at governing equation of the code. This work was done to check the calculation efficiency for small number channel problem as CETOP
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Secondary Subject
Source
Korean Nuclear Society, Daejeon (Korea, Republic of); [1 CD-ROM]; Oct 2010; [2 p.]; 2010 autumn meeting of the KNS; Jeju (Korea, Republic of); 21-22 Oct 2010; Available from KNS, Daejeon (KR); 5 refs, 2 figs, 1 tab
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AbstractAbstract
[en] In accordance with the Act on Physical Protection and Radiological Emergency, nuclear power plant licensees shall have the emergency response facilities in preparation for radiological disasters. The facilities include the main control room (MCR), onsite technical support center (TSC), onsite operational support center (OSC), and near-site emergency operations facility (EOF). This study provides guidance on the criteria and methodology for the evaluation of emergency response facilities
Primary Subject
Source
Korean Nuclear Society, Daejeon (Korea, Republic of); [1 CD-ROM]; Oct 2010; [2 p.]; 2010 autumn meeting of the KNS; Jeju (Korea, Republic of); 21-22 Oct 2010; Available from KNS, Daejeon (KR); 4 refs, 1 fig, 2 tabs
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