Open Access
Issue
EPJ Nuclear Sci. Technol.
Volume 3, 2017
Article Number 37
Number of page(s) 6
DOI https://doi.org/10.1051/epjn/2017032
Published online 12 December 2017
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  6. R.A. Jaramillo et al., Tensile Hoop Behaviour Of Irradiated Zircaloy-4 Nuclear Fuel Cladding, Techanical Report ORNL/TM-2006/163 (Oak Ridge National Laboratory, USA, 2006)
  7. Waseem, N. Elahi, G. Murtaza, Structural integrity assessment and stress measurement of CHASNUPP-1 Fuel assembly, Int. J. Nucl. Eng. Des. 280, 130 (2014) [CrossRef]
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  11. ASME, Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NB, Article NB-3000, 2001

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