Nuclear reactor full-core deterministic computational schemes in transport theory

输运理论中核反应堆全核确定性计算方案

• 批准号: 107847-2011
• 负责人: Hébert, Alain
• 金额: $ 1.97万
• 依托单位: École Polytechnique de Montréal
• 依托单位国家: 加拿大
• 项目类别: Discovery Grants Program - Individual
• 财政年份: 2011
• 资助国家: 加拿大
• 起止时间: 2011-01-01 至 2012-12-31
• 项目状态: 已结题
• 来源: https://www.nserc-crsng.gc.ca/ase-oro/Details-Detailles_eng.asp?id=475438
• 关键词: Nuclear; reactor; full; core; deterministic

We are focusing on full-core reactor physics codes required for simulation of operation, fuel management and safety analyses of third- and fourth-generation reactors. Neutron diffusion theory is currently used for this purpose, but reference calculations require a more accurate representation of transport phenomena. Based on recent advances related to the MOC and to the evolution of computer clusters, we can now propose the implementation of a family of rigorous full-core solution technique relying on the discrete ordinates method (for regular geometries) and on the MOC (for unstructured geometries). The MOC we propose to develop is an original contribution based on:

我们专注于第三代和第四代反应堆运行模拟、燃料管理和安全分析所需的全堆芯反应堆物理代码。中子扩散理论目前用于此目的，但参考计算需要更准确地表示输运现象。基于与 MOC 和计算机集群发展相关的最新进展，我们现在可以提出实施一系列严格的全核解决方案技术，该技术依赖于离散坐标方法（对于规则几何形状）和 MOC（对于非结构化几何形状）。我们建议开发的 MOC 是基于以下内容的原创贡献：