[en] An advanced spent fuel conditioning process (ACP) is developing for the safe and effective management of spent fuels which arising from the domestic nuclear power plants. And its demonstration facility is under design. This facility will be prepared by modifying IMEF's reserve hot cell facility which reserved for future usage by considering the characteristics of ACP. This study presents a basic structural architecture design and analysis results of ACP hot cell including modification of the IMEF. The results of this study will be used for the detail design of ACP demonstration facility, and utilized as basic data for the licensing of the ACP facility

[en] Burnup of the fuel rod and specimens taken from spent nuclear fuel assemblies G23 and C15 discharged from Kori-1 in 1986 and 1982, respectively, was non-destructively determined. And then they were compared with the declared burnup of NPP (nuclear power plant) and destructive chemical burnup. As a result of the comparison, the measured average burnup has a good agreement with the declared burnup within 5 % error in the G23-G2 rod. And there is approximately 4 % difference between the measured and chemically determined burnup at the relatively higher burnup region of the C15-E11 rod, but it appeared to be poor agreement at the lower burnup region in the vicinity of rod ends

[en] A study on the advanced spent fuel conditioning process (ACP) is carring out for the effective management of spent fuels of domestic nuclear power plants. This study presents basic shielding design, modification of IMEF's reserve hot cell facility which reserved for future usage, conceptual and structural architecture design of ACP hot cell and its contents, etc. considering the characteristics of ACP. The results of this study will be used for the basic and detail design of ACP demonstration facility, and utilized as basic data for the safety evaluation as essential data for the licensing of the ACP facility

[en] Advanced spent fuel Conditioning Process(ACP) project which is under development for efficient spent fuel management has finished process feasibility study and is preparing α-ν type hot cell construction for process experimentation. Radiation dose evaluation for the radioactive nuclides were preliminarily performed for normal operation and accident case with the basic concept design report, the meteorologic all data and the recent site specific data. According to the production and release rate of nuclides, dose evaluations for residents around facility were performed. The evaluation result shows a safe margin for regulation limits and SAR limit of IMEF where this facility will be constructed

[en] A periodic inspection for the KSC-1 cask which has been used for the transportation of the spent nuclear fuel assemblies was carried out to confirm the integrity of the cask according to the national law and the regulations of the atomic energy. This report describes inspection procedures, results of each items, detailed processes for the leakage and shielding evaluation, and concrete methods relevant to a modeling and a calculation tool to present criteria for the integrity of the cask in the leakage test and the shielding performance test. Especially, this report shows the burnup peaking factor required in the shielding calculation. It reveals that the peaking factor has no dependency on the rod average burnup and the peaking factor was determined as value of 1.22 through the statistical treatment

[en] The Advanced spent fuel Conditioning Process (ACP) is under development for the effective management of spent fuel which had been generated in nuclear plants. The ACP needs a hot cell where most operations will be performed. To give priority to the environment safety, radiation doses evaluation for the radioactive nuclides was preliminarily performed with the basic concept design report, the meteorological data and the recent site specific data. According to the production and release rate of nuclides, dose evaluations for residents around facility were performed. The evaluation result shows a safe margin for regulation limits and SAR limit of IMEF where this facility will be constructed

[en] A design work is conducting for the IMEF's future cell which located in the basement to use it as a demonstration facility for Advanced Spent Fuel Conditioning Process (ACP). Since the total radiation source which used in ACP is expected as approximately 10 times higher than the design criteria of IMEF, the existing concrete structure cannot meet the shielding requirements. Therefore, shielding design which reinforcing the shielding capability has carried out for the ACP hot cell to satisfy the shielding criteria for the expected maximum radioactivity of ACP. This study presents a shielding analysis results using QADS code for the reinforced shielding wall with heavy concrete, steel or lead, etc. As a results of the analysis, a shielding wall reinforcing method was proposed. Additional shielding analysis was performed for the ACP hot cell with proposed reinforced shielding design using MCNP-4C code, and the validity of radiation shielding design was evaluated

[en] The Advanced spent fuel Conditioning Process (ACP) is under development for the effective management of spent fuel which had been generated in nuclear plants. The ACP needs a hot cell where most operations will be performed. To give priority to the environment safety, radiation doses evaluation for the radioactive nuclides was preliminarily performed with the basic concept design report, the meteorological data and the recent site specific data. According to the production and release rate of nuclides, dose evaluations for residents around facility were performed. The evaluation result shows a safe margin for regulation limits and SAR limit of IMEF where this facility will be constructed

[en] The advanced spent fuel conditioning process (ACP) was proposed for effective management of the PWR spent fuel. The ACP is under developing as R and D project, and this project includes detail plan for verification of the ACP. An exisiting hot cell was selected for demonstration of the ACP. But this hot cell should be modified to meet requirements for effective and safe operation of this process. In this study, the process and hot cell design were performed, and the results were suggested. And then, this results will be utilized for hot cell refurbishment and license

[en] In order to evaluate the long term storage safety study of the metallic spent fuel, U-5Zr, U-5Ti, U-5Ni, U-5Nb, and U-5Hf simulated metallic uranium alloys, known as corrosion resistant alloys, were fabricated and oxidized in oxygen gas at 200 .deg. C ∼ 300 .deg. C. All simulated metallic uranium alloys were more corrosion resistant than pure uranium metal, and corrosion resistance increases Nb, Ni, Ti, Zr, Hf in that order. The oxidation rates of uranium alloys determined and activation energy was calculated for each alloy. The matrix microstructure of the test specimens were analyzed using OM, SEM, and EPMA. It was concluded that Nb was the best acceptable alloying elements for reducing corrosion of uranium metal, and Ni, Ti were also considered to suitable as candidate