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AbstractAbstract
[en] MCNPX computer code is used to model the general cask GBC-32 which contain 32 typical PWR spent fuel assemblies. For Safe storage and transportation of the cask, factors that affect the criticality were studied using the concept of burn up credit. Several parameters such as initial fuel enrichment, fuel burnup, cooling time, and axial burnup profile were analysed. The analysis was performed in two different steps, first burn the fuel assembly at different burnup and storage conditions, secondly, incorporate the details of the assemblies into the cask and perform a criticality calculations for the cask. Several cases of unnormal storage conditions are considered. The results are compared with similar GBC-32 benchmark. (author)
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International Atomic Energy Agency, Division of Nuclear Fuel Cycle and Waste Technology and Division of Radiation, Transport and Waste Safety, Vienna (Austria); OECD Nuclear Energy Agency, Paris (France); European Commission, Brussels (Belgium); World Nuclear Association, London (United Kingdom); [1 CD-ROM]; ISBN 978-92-0-108620-4;
; May 2020; 9 p; International conference on management of spent fuel from nuclear power reactors: Learning from the past, enabling the future; Vienna (Austria); 24-28 Jun 2019; IAEA-CN--272/67; ISSN 0074-1884;
; Also available on-line: https://www.iaea.org/publications/14680/management-of-spent-fuel-from-nuclear-power-reactors?supplementary=82942; Enquiries should be addressed to IAEA, Marketing and Sales Unit, Publishing Section, E-mail: sales.publications@iaea.org; Web site: http://www.iaea.org/books; 9 refs., 7 figs., 8 tabs.


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Conference
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