Thermal hydraulic & neutronic analysis of dry cask storage systems for spent nuclear fuels
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Date
2000-10
Authors
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Journal ISSN
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Publisher
Turkish Atomic Energy Authority
Abstract
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).
Description
I. Avrasya Nükleer Bilimler ve Uygulamaları Konferansı : 23-27 Ekim 2000. İzmir, Türkiye.
Keywords
Spent nuclear fuels, Tükenmiş nükleer yakıtlar, Dry cask storage systems, Kuru hazne depolama sistemleri, Thermal hydraulic & neutronic analysis, Termal hidrolik ve nötronik analiz
Citation
Yavuz, U., Zabunoğlu, H. O., (2000). Thermal hydraulic & neutronıc analysis of dry cask storage systems for spent nuclear fuels. I. Eurasia Conference on Nuclear Science and Its Application, Presentations, Vol 1, (s. 328-332). 23-27 October 2000. İzmir, Turkey.