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The Current Status of Spent Nuclear Fuel in Korea
Pages 109-117

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From page 109...
... , was commissioned in Korea in April 1978, the nuclear power generation capacity has grown steadily and remarkably in Korea. By the end of 2002, 18 nuclear power plants with 14 PWRs and 4 CANDU (Canada deuterium uranium)
From page 110...
... The government effort to construct a centralized interim storage facility for spent fuel and a repository for radioactive waste packages had come to nothing due to strong dissension about the site acquisition from the local communities. After the Guleop Island Project was
From page 111...
... For PWRs the AR expansion is currently being carried out by transshipment between neighboring units and re-racking with high-density storage racks, which increase the storage density by using boral or borated stainless steel neutron absorbers, have been installed partially or fully in spent fuel pools. Storage density was increased to about 200 percent by replacing old storage racks with the high-density storage racks.
From page 112...
... From this context a broad feasibility study was performed from 1991 to 1993 in order to identify any feasibility issues of a fundamental nature for the DUPIC fuel cycle concept. This concept is based on the idea that the spent PWR fuel material is fabricated directly into CANDU fuel without any intentional separation of fissile materials and fission products.
From page 113...
... to characterize DUPIC powder/pellets using actual spent PWR fuel, a main DUPIC fuel fabrication campaign was started to fabricate the DUPIC fuel pellets and elements for the irradiation test at a research reactor. From the start of this experiment until the year 2002 a total of 10 kg of spent PWR fuel that has undergone a nominal burn-up of 35,500 MWd/tU was fabricated into DUPIC fuel pellets and elements.
From page 114...
... code development ­ cyber research and development platform development ­ flow visualization lab provision · assessment of deep geological environmental condition · validation of performance of high-level waste disposal system ­ engineered barrier systems (EBS) performance experiments in engineer ing scale ­ radionuclide migration experiments in large rock block ­ construction and operation of underground research tunnel at KAERI site Advanced Spent Fuel Conditioning Process With the volume reduction perspective of the spent fuels to be stored and/or disposed of, the Advanced Spent Fuel Conditioning Process, a so-called lithium reduction process, has been under development in KAERI since 1997.
From page 115...
... Nuclear materials control and accounting technology for this process is being developed. More detailed research and development items are being performed as follows: · optimization of process systems by using mockup facilities · experimental verification of oxide reduction chemistry · automation and remotization of all unit operations and material transfers between operations · development of nuclear materials control and accounting technology · establishment of continuous uranium metal casting technology · selection and optimization of dry storage systems The planned launch date of the Phase III study of this project is 2004, and the study will cover lab-scale verification of process concepts, demonstration of nuclear material accountability and system safeguardability, verification of technical and economic feasibility of the process concepts, and the establishment of a roadmap for further research and development.
From page 116...
... The basic concept of the DUPIC fuel cycle is to directly fabricate the CANDU fuel from the spent PWR fuel by using thermal/mechanical processes at hot cells without the separation of fission products and transuranic elements. Since 1991 KAERI has successfully fabricated several DUPIC fuel elements remotely in the hot cell, and the performance evaluation through the irradiation tests at the HANARO research reactor is under way.
From page 117...
... The purpose of the study on the pyroprocess for partitioning and ADS for transmutation is to propose a conceptual design of the HYPER system by 2006. In this study, the HYPER system, comprising a proton accelerator and a subcritical reactor, is considered an appropriate one for the Korean situation, with priority given to the nonproliferation attributes of the treatment of nuclear fissile materials in the back-end fuel cycle.


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