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Chun, Yong Bum; Min, D. K.; Son, Y. J.
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2009
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2009
AbstractAbstract
[en] The operation of the PIE facility in 2008 preferentially aimed at the safety. Especially, we focused on the safe operation, the employee's safety, and the prevention of radioactive materials leakages. The PIE for the PLUS7-type fuel rods which were developed by KNF was conducted to establish data base related to the irradiation performance evaluation. NDT for ten spent fuel rods and DT for six rods were carried out. Additionally, six RFA-type spent fuel rods irradiated at Gori unit-3 NPP were transported to the PIEF and the preliminary NDTs on 4 rods among them were performed. PIEs conducted to support the mid and long term R and D project were as follows; Post-irradiation Annealing test for the spent nuclear fuel, Installation and performance test of the integrated neutron-gamma detection device for the spent nuclear fuel, Measurement of the neutrons emitted from the spent fuel in the pool, and PIE for crud analysis of the high-burnup spent nuclear fuel. PIEF achieved the goal of the accident-free operation in 2008. The major safety equipment were inspected periodically and the facility was also maintained to be safe by a planned inspection from the external expert organization. Especially, the structure safety diagnosis of the PIEF was carried out for three months and the repairing plan was made according to the diagnosis result. Also, the nuclear transparency of the facility was verified by the random inspection after two hours advance notice for the first time, as Korea approached one step more to 'Integrated Safeguard'. We made an effort to strengthen the PIE capability in 2008. According to the demand and request, the development of hot cell measurement techniques and devices were driven forward. The Studies about quantification analysis of Xe/Pu using the wavelength dispersive spectroscope (WDS) and the gamma scanning technique for the spent fuel were proceeded continuously after last year. And the development of the sample preparation technique was conducted in order to measure precisely the dimension of the dual cooled annular fuel pellet, which has been irradiated in HANARO research reactor at present time. PIE facility operated for more than twenty years has need of the budget to renovate those deteriorated equipment for a continuous R and D support. A various budget sources should be considered in order to answer the purpose of safety and to meet the demands for a higher technology of the PIE services. Also, an appropriate support of the manpower are strongly required to maintain the technical know-how of PIE expertises
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Source
Jan 2009; 215 p; Also available from KAERI; 5 refs, 106 figs, 106 tabs
Record Type
Report
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ENERGY SOURCES, ENRICHED URANIUM REACTORS, EQUIPMENT, FUEL ELEMENTS, FUELS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, LABORATORY EQUIPMENT, MATERIALS, MATERIALS TESTING REACTORS, NUCLEAR FUELS, POOL TYPE REACTORS, REACTOR COMPONENTS, REACTOR MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, TEST FACILITIES, TEST REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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