Open Access
Issue
EPJ Nuclear Sci. Technol.
Volume 2, 2016
Article Number 16
Number of page(s) 10
DOI https://doi.org/10.1051/epjn/2016010
Published online 01 April 2016
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  8. C.L. Wheeler et al., COBRA-IV-I: an interim version of COBRA for thermal-hydraulic analysis of rod-bundle nuclear fuel elements and cores, Battelle Pacific Northwest Laboratories Report, BNWL-1962, 1976
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