Browsing by All Authors "Yavuz, Ufuk"

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    Illicit trafficking of nuclear material and other radioactive sources
    (Turkish Atomic Energy Authority, 2000-10) Yılmazer, Ayhan; Yücel, Aysun; Yavuz, Ufuk; 169974; TAEK-NGD
    As it is known, for the fact that the illicit trafficking and trading of nuclear materials are being increased over the past few years because of the huge demand of third world states. Nuclear materials like uranium, plutonium, and thorium are used in nuclear explosives that has very attractive features for crime groups, terörist groups and, the states that are willing to have this power. Crime groups that make illegal trade of nuclear material are also trying to market strategic radioactive sources like red mercury and Osmium. This kind of illegal trade threats public safety, human health, environment also it brings significant threat on world peace and world public health. For these reasons, both states and international organizations should take a role in dealing with illicit trafficking. An important precondition for preventing this kind of incidents is the existence of a strengthened national system for control of all nuclear materials and other radioactive sources. Further, Goverments are responsible for law enforcement within their borders for prevention of illegal trading and trafficking of nuclear materials and radiation sources
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    Thermal hydraulic & neutronic analysis of dry cask storage systems for spent nuclear fuels
    (Turkish Atomic Energy Authority, 2000-10) Yavuz, Ufuk; Zabunoğlu, H. Okan; TAEK-NGD
    Interim spent fuel storage systems must provide for the safe receipt, handling, retrieval and storage of spent nuclear fuel before reprocessing or disposal. In the context of achieving these objectives, the following features of the design were taken into consideration for metal shielded type storage systems; to maintain fuel subcritical, to remove spent fuel residual heat, to provide for radiation protection. These features in the design of a dry cask storage system were analyzed by employing COBRASFS and SCALE4.4 (ORIGEN, XSDOSE, CSAS6 ) codes for normal operation of the system under study. In accordance with safety assurance limits of International Atomic Energy Authority (IAEA), appropriate designs for Dry Cask Storage Systems (DCSS) were reached for 33000, 45000, and 55000 MWd/t bumup values and 5 and 10 years of cooling periods for spent fuel to be stored (Table 1).