| Taking a spent fuel shipping cask as calculated model, detailed criticality safety, nuclear heat distribution and shielding calculations and sensitivity analysis of some parameters were performed. Burnup-credit analysis sequence STARBUCS in SCALE5.1 code system was used to complete criticality safety calculation, and one-dimensional discrete ordinates code SAS2 and three-dimensional Monte Carlo code SAS4 were used to perform shielding calculation. Monte Carlo code MCNP and discrete-ordinates code DORT and point-kernel code QAD were chosen to perform comparative calculation in order to ensure the availability of SAS2 and SAS4. Criticality calculation shows that shipping cask is safe. Dose rate profile and nuclear heat distribution were also calculated respectively. These calculations can supply reference for design and production of shipping cask and safe transport of spent fuel.
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