[en] A method to consider temperature dependent material properties when using the Green's function method is proposed by using a numerical weight function approach. This is verified by using detailed finite element analyses for a pressurizer spray nozzle of KORI 1 with various assumed thermal transient load cases

[en] As the liquid sodium of a sodium-cooled fast reactor (SFR) is opaque to light, a conventional visual inspection is unavailable for the evaluation of the in-vessel structures under a sodium level. ASME Section XI Division 3 provides rules and guidelines for an in-service inspection (ISI) and testing of the components of SFR. For the ISI of in-vessel structures, the ASME code specifies visual examinations. An ultrasonic wave should be applied for an under-sodium visual inspection of the in-vessel structures. The plate-type waveguide sensor has been developed and the feasibility of the waveguide sensor technique has been successfully demonstrated for an ultrasonic visual inspection of the in-vessel structures of SFR. In this study, the C-scan image mapping program (Under-Sodium MultiView) is developed to apply this waveguide sensor technology to an under-sodium visual inspection of in-vessel structures in SFR by using a LabVIEW graphical programming language. The Under-Sodium MultiVIEW program has the functions of a double rotating scanner motion control, a high power pulser receiver control, a image mapping and a signal processing. The performance of Under-Sodium MultiVIEW program was verified by a C-scanning test

[en] The design for arranging main components and piping system of Intermediate Heat Transport System(IHTS) of KALIMER- 600 with 2-loop and 3-loop was performed. Displacements, stresses were calculated for dead weight and thermal load under normal operation condition about 2-loop system and 3-loop system. Evaluation results of IHTS piping system by ASME-NH code showed that stress intensity and creep-fatigue damage were satisfied their limits. The natural frequencies of the two systems were calculated to check the dynamic characteristics related to the plant isolation frequency of 0.5Hz. ANSYS 6.1 structural analysis module was used of stress analysis and natural frequency calculation

[en] In order to reduce the construction cost of the fuel transfer system, the simplification of the components and the reduction of the size for the reactor building and the fuel handling and storage building are important. In this report, the economic concept is analyzed and suggested through the design simplification of the fuel handling system in KALIMER-600. The verification for the deformation of the reactor core structures is necessary during the refueling time and the inspection for the main parts of the other reactor internal structures is required in SFR. The functions of the IVTM and the inspection machine of the reactor internal structure were integrated by the unification. The concept of the integrated in-vessel transfer and inspection machine is derived in combination with the IVTM which handle the fuel assemblies of the reactor core and the inspection machine which can verify the measurement position and the deformation, can simultaneously perform the detection of the existence of obstacles on the moving path and the mapping for the core top region

[en] The theoretical and experimental study of the propagation and radiation of leaky Lamb wave in a plate waveguide sensor has been carried out. In the plate waveguide sensor, the A₀ leaky Lamb wave is utilized for the single mode generation and the effective radiation capability in a fluid. The plate waveguide sensor which consists of a plate waveguide, a teflon wedge and an ultrasonic sensor has been designed and manufactured. The tone-burst excitation of high power long pulse should be applied to minimize the dispersion effect in 10 m long distance propagation of the A₀ Lamb wave. A novel technique which is capable of steering a radiation beam of a waveguide sensor without a mechanical movement can be achieved by a frequency tuning method of the excitation pulse in the dispersive low frequency range of the A₀ Lamb wave. The characteristics of radiation beam of ultrasonic waveguide sensors has been investigated by the beam profile measurements according to the plate thickness, the radiation aperture length, the pulse cycles and the excitation frequency. The design parameters of the plate waveguide sensor has been optimized. The C-scanning experiments in water have been carried out for the performance of the optimized ultrasonic waveguide sensor. The poulsbility of C-scan visualization using the plate waveguide sensor has been verified

[en] This report is a draft of an enactment of KEPIC MNH based on 2007 ASME Boiler and Pressure Vessel Code, Section III, Division 1 Subsection NH for Class 1 Components in Elevated Temperature Service and contains of ASME Article NH-3000 design, the mandatory appendix I-14, and non-mandatory appendices T and X

[en] In this report, the activities of KAMC (Korea ASME Mirror Committee), which is sponsored by Korea Standard Association, are described in detail

[en] Summary: • A new idea and concept of plate-type ultrasonic waveguide sensor and inspection technique have been suggested for under-sodium viewing; • Development of 10m long waveguide sensor modules and visualization software program; • Feasibility verification of 10 m waveguide sensor modules in water; • Development of under-sodium ultrasonic waveguide sensor with Be and Ni coating layers; • Setup of sodium test facility and performance demonstration of undersodium waveguide sensor in sodium

[en] The structural features of BREST-300 and INEEL's Lead-cooled LMR models were figured out to help developing the reactor structures of 900MWt Lead-cooled LMR of Korea. The preliminary structural integrity was assessed based upon the assumption of the reactor structure, thermal loading, and vertical seismic loading. Also, creep damage was evaluated utilizing ASME NH code. From the analysis results, it was proposed that the appropriate thickness of guard vessel was 10cm and the proposed design showed the proper structural integrity. It is necessary to develop shape of reactor structure including supports and to perform more detailed thermal and structural analyses considering environmental effects

[en] A high temperature structural integrity assessment belongs to the Part II of a whole preliminary guideline for the high temperature structure. The main contents of this guideline are the evaluation procedures of the creep-fatigue crack initiation and growth in high temperature condition, the high temperature LBB evaluation procedure, and the inelastic evaluations of the welded joints in SFR structures. The methodologies for the proper inelastic analysis of an SFR structures in high temperatures are explained and the guidelines of inelastic analysis options using ANSYS and ABAQUS are suggested. In addition, user guidelines for the developed NONSTA code are included. This guidelines need to be continuously revised to improve the applicability to the design and analysis of the SFR structures