Abstract
The back-end of the fuel cycle concept for spent High-Temperature Reactor fuel elements in Germany is based upon intermediate storage in shielded casks in a surface facility followed by direct disposal in a deep repository. Two storage facilities are in operation, whereas disposal in a salt dome repository is being designed. R&D results obtained so far support the chosen concept and underline the special safety features of the fuel elements, i.e. the coated particle fuel stabilised in a graphite matrix, which is extremely resistant against all conceivable attacks during storage and disposal.
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