Abstract
To provide a cask with the largest possible loading capacity of spent fuel assemblies with the largest practicable burnup and shortest cooling time within all safety requirements, AREVA TN has adapted its design process and developed a more elaborated shielding analysis method. Taking advantage of the potential heterogeneities between sources of fuel assemblies to be loaded, and the self-shielding of assemblies loaded at the basket centre by the assemblies loaded at the basket periphery, the result of this method is expressed under the shape of a linear inequalities system allowing to optimize the cask capacity and performance.
Highlights
Fuel assembly characteristics are evolving in order to improve performance of reactor operations
Regarding the maximum radiation levels generated at the contact of the TN®9-4 cask external surface, in the different axial and radial areas defined with an adapted external surface map (Fig. 1), the detailed shielding analysis performed allows reducing the fulfilment of the radiation level threshold, only
The linear inequalities system, resulting from the new shielding analysis method developed by AREVA TN, presents a high implementation flexibility and allows taking advantage of the explicit characteristics of the fuel assembly inventory
Summary
Fuel assembly characteristics are evolving in order to improve performance of reactor operations. To improve cask performance with the largest possible loading capacity of spent fuel assemblies, the largest practicable burnup and shortest cooling time while conforming to all safety requirements, AREVA TN has adapted its design process and has developed a more elaborated shielding analysis method to meet the latest regulatory recommendations. This new method avoids to develop a safety demonstration based on a loading plan matrix with a limited number of homogeneous and non homogeneous loading options
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