[en] In a number of applications it is required to work for a long periods of time on the ocean, where supply of fuel is complicated and sometimes impossible. Moreover, high efficiency and compactness are the other important requirements in naval application. Therefore, an integrated nuclear electric propulsion system is the best choice to meet all of these requirements. In this paper, a modeling of nuclear electric propulsion for naval application is presented. The model adopted a long-term power system dynamics model to represent the dynamics of nuclear power part

[en] For the evaluation of a failure mode for Motor Control Centers (MCCs), a shaking table test already performed by Kim et al. In this study, the seismic fragility was evaluated by using previous shaking table test results. At first, amplification results according to the shaking table test about 480V MCCs analyzed according to a method of NUREG/CR-5203. Secondly, the seismic fragility of 480V MCC was evaluated according to the methodology that was introduced in the report EPRI TR-103959. Through this study, it can be concluded that the seismic fragility results of the PSA report in Korea were underestimated

[en] An infrared (IR) sensor is a tool most generally used in physical protection systems (PPS) within Korean nuclear power plants (NPP). Consumer manuals are used to help assemble, install and maintain IR sensors. However, the manuals only provide information on the general conditions of a nuclear power plant, and not on the specific characteristics of a plant. In order to provide more specific information, a Test-Bed was constructed and operated. The Test-Bed was an experimental platform used for assessing the performance of the detection and delay functions of a physical protection system (PPS). This paper discusses the process and results obtained from the performance evaluation of the IR sensor

[en] The fast neutron generation facility based on a recently developed D-D neutron generator is constructed at Seoul National University. The fast neutron generation facility will be used for the research and the education of undergraduate and graduate students. In this paper, the procedure of the constructing of the fast neutron generation facility is described

[en] We have the experience developing radiation imaging detector using single-sided silicon strip sensor. Based on that, in this time, we developed an imaging detector to study the feasibility of our double-sided silicon strip sensor for imaging applications

[en] Vibration is one of physical phenomena to affect capability and life cycles in turbo machinery. Vibration of most turbo machinery is caused by unbalanced mass, which leads turbo machinery to be damaged or failed before design life This research tried to optimize the effect on operation of Reactor Coolant Pump(RCP) due to the improvement of structure

[en] The SFR (Sodium Fast Reactor) which is being developed at KAERI (Korea Atomic Energy Research Institute) is currently divided into three types, such as, Advanced Concept 600 MWe break-even reactor and burner reactor and 1200 MWe break-even reactor. As a part of accidents analysis of the 600 MWe break-even reactor, 5 representative DBE's (Design Bases Events) are analyzed for the safety analysis. The 5 DBE's are TOP (Transient of Over Power), LOF (Loss Of Flow), LOHS (Loss Of Heat Sink), Pipe Break, and SBO (Station Black Out)

[en] The STEF(Sodium Thermal-Hydraulic Experimental Facility) is a passive decay heat removal circuit test facility for simulating thermal hydraulic behavior of the Korean demonstration fast reactor under development by KAERI(Korea Atomic Energy Research Institute). The KALIMER-600 is a prototype fast reactor whose conceptual design was finished in early 2007. Since the capacity of the demonstration Korean fast reactor has not been yet determined, the preliminary design of the STEF was based on the KALIMER-600. In this paper, the overall preliminary design features of the STEF are introduced, and issues in mechanical design and fabrication of the experimental test facility are described

[en] Zirconium alloys have anisotropic mechanical properties depending on their physical orientations because of the formation of texture in their microstructures. In order to investigate the creep anisotropy depending on geometrical orientations, HANA-6 (Zr-1.1Nb-0.07Cu) alloy strips with different orientations were used. The experimental results will be presented in another paper. In this paper, the anisotropic creep behaviors will be interpreted by introducing a basic slip mechanism

[en] The analyses of piping systems under dynamic conditions such as pipe ruptures and abnormal valve operations are important to a safety evaluation. Hydrodynamic forces in the piping system can be computed by using the hydraulic output from the RELAP5/MOD3.1. In this study, hydrodynamic forces were computed by two different methods. One is a force-balanced method and the other is a momentum-balanced method. The purpose of this study is to compare hydrodynamic forces resulting from two methods