Improved CANDU-core homogenization and benchmark models

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For CANDU reactors to continue to be an important contributor to the Ontario energy supply they have to satisfy ever increasing economic and safety demands. In particular, increasingly accurate and detailed simulation models are required for the safety analysis of existing, as well as future, CANDU reactors. The broad objective of this work is twofold: To develop a new, more accurate, method for calculating the neutron power distribution in a nuclear reactor by using advanced homogenization methods and to develop detailed CANDU-specific benchmark problems to test the newly-developed method, as well as other methods and codes in current use in the Canadian nuclear industry.