Improved CANDU-core homogenization and benchmark models

为了使CANDU反应堆继续成为安大略能源供应的重要贡献者，它们必须满足日益增长的经济和安全需求。 特别是，越来越准确和详细的模拟模型需要现有的，以及未来的CANDU反应堆的安全分析。 这项工作的广泛目标是双重的：开发一种新的，更准确的方法，用于计算在核反应堆中的中子功率分布，通过使用先进的均匀化方法，并制定详细的CANDU特定的基准问题，以测试新开发的方法，以及其他方法和代码，目前在加拿大核工业中使用。 新开发的改进的均化方法将提高加拿大工业专家和研究人员分析现有反应堆和设计新反应堆的模拟工具的准确性。 开发的CANDU基准将用于评估现有的以及新兴的反应堆物理计算工具。

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. The newly-developed improved homogenization methods will increase the accuracy of simulation tools available to Canadian industry specialists and researchers for the analysis of existing reactors and for the design of new reactors. Developed CANDU benchmarks will be used for the evaluation of existing as well as emerging reactor-physics computational tools.