ACR FUEL STORAGE ANALYSIS: FINITE ELEMENT HEAT TRANSFER ANALYSIS OF DRY STORAGE

摘要

Over the past decade Atomic Energy of Canada Limited (AECL) has designed and licensed air-cooled concrete structures used as above ground dry storage containers (MACSTOR~(~R)) to store irradiated nuclear fuel from CANDU plants. A typical MACSTOR~(~R) 200 module is designed to store 12,000 bundles in 20 storage cylinders. MACSTOR~(~R) 200 modules are in operation at Gentilly-2 in Canada and at Cernavoda in Romania. The MACSTOR~(~R) module is cooled passively by natural convection and by conduction through the concrete walls and roof. Currently AECL is designing the Advanced Candu Reactor (ACR~(~R)) with CANFLEX slightly enriched uranium fuel to be used. AECL has initiated a study to explore the possibility of storing the irradiated nuclear fuel from ACR in MACSTOR modules. This included work to consider ways of minimizing footprint both in the spent fuel storage bay and in the dry storage area. The commercial finite element code ANSYS has been used in this study [1]. The FE model is used to complete simulations with the higher heat source using the same concrete structural dimensions to assess the feasibility of using the MACSTOR design for storing the ACR irradiated fuel. This paper presents the results of the analysis. The results are used to confirm the possibility of using, with minimal changes to the design of the storage baskets and the structure, the proven design of the MACSTOR~(~R) 200 containment to store the ACR fuel bundles with higher enrichment and burnup. This has thus allowed us to confirm conceptual feasibility and move on to investigation of optimization.