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[en] This lengthy treatment of the collision of atoms studies electron-atom collision, instead of ion-atom, because the former are better understood, and comparison with ions will help understanding ions. A series of lectures is outlined as follows. Theory of Fast Collision: The Born Approximation is studied first. The basic formulas--plane wave Born (PWBA), Coulomb Born Approximation (CBA), Distorted wave Born approximation (DWBA) are investigated, and generalized. Integrated crosssections in PWBA, the Fano plot, and line strength, and comparison of PWBA, CBA, and DWBA in discrete excitation concludes the study of the Born Approximation. Ionization by electron impact is studied next. Cross sections, angle distribution, and energy distribution of secondary electrons are among the points touched on in electron impact study. Total ionization cross-section is then treated for fast, intermediate, and low incident energies. Relativistic kinematics and electron correlation studies follow. The theory of slow collisions, second Born, Glauber, and close coupling approximations are considered under this heading

[en] This report describes all the major results of the dynamic structural analysis and seismic design for the Cold Neutron Laboratory Building which is classified in seismic class II. The results are summarized of the ground response spectrum as seismic input loads, mechanical properties of subsoil, the buoyancy stability due to ground water, the maximum displacement of the main frame under the seismic load and the member design. This report will be used as a basic design report to maintenance its structural integrity in future

[en] The analysis of load flow is for searching the optimal operation condition by computer simulation. The analyzed items are as follows. Active and reactive power from KAERI substation. Voltage drop on Tus. Analysis of load flow of active power and reactive power on Bus The motor starting current of most ac motors is several times normal full load current. Motor starting torque varies directly as square of the applied voltage. If the terminal voltage drop is excessive, the motor may not have enough starting torque to accelerate up to running speed. Running motors may stall from excessive voltage drops. Short-circuit studies are done to determine the magnitude of the prospective currents flowing throughout the power system at various time intervals after a fault occurs. Short-circuit studies can be performed at the planning stage in order to help finalize the system layout, determine voltage levels, and size cables, transformers, and conductors. For existing systems, fault studies are necessary in the cases of installation of extra rotating loads, system layout modifications, rearrangement of protection equipment, verification of the adequacy of existing breakers. This technical report deals with the load flow study, motor starting study and short circuit study for CNS(Cold Neutron Source) power system using ETAP(Electrical Transient Analyzer Program) to determine the optimal operating condition

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[en] It is important to know the effect of a local flow blockage on the potential of localized boiling and a failure of the fuel cladding within an LMR fuel subassembly. In this study, flow blockage is simulated by using the subchannel analysis codes, MATRA-LMR and SABRE4 with THORS experimental data of ORNL. Both codes show relatively good agreement to the experimental data for exit temperatures in no blockage case. But in blockage case, there were some differences between the experimental data and the code calculational results. Solid blockage could not be exactly predicted by MATRA-LMR because of the numerical instabilities of this code

[en] Although it is expected that the decommissioning of a nuclear power plant will happen since 2020, the need of partial decommissioning and decontamination for periodic inspection and life extension has been on an increasing trend and domestic market has gradually been extended. Therefore, in this project the decommissioning DB system on the KRR-1 and 2 was developed as establishing the information classification system of the research reactor dismantling and the structural design and optimization of the decommissioning DB system. Also in order to secure the reliability and safety about the dismantling process, the main dismantling simulation technology that can verify the dismantling process before their real dismantling work was developed. And also the underwater cutting equipment was developed to remove these stainless steel parts highly activated from the RSR. First, the its key technologies were developed and then the design, making, and capability analysis were performed. Finally the actual proof was achieved for applying the dismantling site. an automatic surface contamination measuring equipment was developed in order to get the sample automatically and measure the radiation/radioactivity

[en] UO₂ kernel fabrication technology was developed at the lab sacle(20∼30g-UO₂/batch). The GSP technique, modified method of sol-gel process, was used in the preparation of spherical ADU gel particle and these particles were converted to UO₃ and UO₂ phases in calcination furnace and sintering furnace respectively. Based on the process variables optimized using simulant kernels in 1-2 inch beds, SiC TRISO-coated particles were fabricated using UO₂ kernel. Power densities of TRISO coated particle fuels and gamma heat of the tubes are calculated as functions of vertical location of the fuel specimen in the irradiation holes by using core physics codes, MCNP and Helios. A finite model was developed for the calculations of temperatures and stresses of the specimen and the irradiation tubes. Dimensions of the test tubes are determined based on the temperatures and stresses as well as the gamma heat generated at the given condition. 9 modules of the COPA code (MECH, FAIL, TEMTR, TEMBL, TEMPEB, FPREL, MPRO, BURN, ABAQ), the MECH, FAIL, TEMTR, TEMBL, TEMPEB, and FPREL were developed. The COPA-FPREL was verified through IAEA CRP-6 accident benchmarking problems. KAERI participated in the round robin test of IAEA CRP-6 program to characterize the diameter, sphericity, coating thickness, density and anisotropy of coated particles provided by Korea, USA and South Africa. The inspection and test plan describing specifications and inspection method of coated particles was developed to confirm the quality standard of coated particles. The quality inspection instructions were developed for the inspection of coated particles by particle size analyzer, density inspection of coating layers by density gradient column, coating thickness inspection by X-ray, and inspection of optical anistropy factor of PyC layer. The quality control system for the TRISO-coated particle fuel was derived based on the status of quality control systems of other countries

[en] The HANARO Cold Neutron Research Facility (CNRF) Project has been embarked in July 2003. The CNRF project has selected as one of the radiation technology development project by National Science and Technology Committee in June 2002. In this report, the output of the second project year is summarized as a basic design of cold neutron source and related systems, neutron guide, and neutron scattering instruments