Development of advanced leakage models for lattice calculations based on the method of characteristics.

本研究项目的长期目标是开发和实现基于输运晶格码的新的或改进的数值模拟技术，使其成为分析核反应堆中中子行为的更精确和有效的工具。这意味着：开发新的计算模型来处理更复杂的系统；编程鲁棒法加速大中子输运问题求解算法利用计算机技术的最新进展开发计算方案。我们提出的大部分开发将在我们在蒙特利尔理工大学开发的代码DRAGON中实现。这个免费分发的软件在加拿大和国外用于candu的安全分析，以及在世界各地的实验室和大学用于先进的反应堆研究。

The long-term objectives of this research program are to develop and implement in transport based lattice codes new or improved numerical simulation techniques to make them more precise and efficient tool to analyse neutrons behaviour in nuclear reactor. This implies: developing new computational models to treat more complex systems; programming robust method to accelerate the solution algorithm for large neutron transport problems; and developing computation schemes benefiting from recent advances in computer technology. Most of the development we proposed will be implemented in the code DRAGON we developed at Polytechnique Montreal. This freely distributed software is used in Canada and abroad for the safety analysis of CANDUs as well as in Laboratories and Universities throughout the world for advanced reactor studies.