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Spent fuel canister for geological repository: Inner material requirements and candidates evaluation
Authors:Francesc Puig  Javier Dies  Aurora Martínez-Esparza
Affiliation:a Departament de Física i Enginyeria Nuclear, Universitat Politècnica de Catalunya, Av. Diagonal, 647, ETSEIB - Pavelló C, Campus Sud - UPC, 08028 Barcelona, Spain
b Departament d’ Enginyeria Química, Universitat Politècnica de Catalunya, Av. Diagonal, 647, ETSEIB - Edifici H, 4a Planta, Campus Sud - UPC, 08028 Barcelona, Spain
c Enresa (Empresa Nacional de Residuos Radiactivos), C/Emilio Vargas, 7, 28043, Madrid, Spain
Abstract:One of the key aspects in designing Spanish spent nuclear fuel canister for geological repository is selecting the inner material to be placed between the steel walls and the fuel assemblies. This material has to primarily avoid the possibility of a criticality event once the canister gets breached by corrosion and flooded by groundwater. A detailed set of requirements for a material to fulfil this role in that environment have been devised and presented in this paper. With these requirements in view, eight potentially interesting candidates were evaluated: cast iron or steel, borosilicate glass, spinel, depleted uranium, dehydrated zeolites, haematite, phosphates, and olivine. Among these, the first four materials or their families are found promising for this application.
Keywords:28  41  Kw  28  52  Fa
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