Development of a generalized perturbation theory model for uncertainty propagation in lattice cell codes

格子码中不确定性传播的广义微扰理论模型的开发

基本信息

批准号：
195505-2006
负责人：
Marleau, Guy
金额：
$ 2.04万
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：
2008
资助国家：
加拿大
起止时间：
2008-01-01 至 2009-12-31
项目状态：
已结题

来源：
https://www.nserc-crsng.gc.ca/ase-oro/Details-Detailles_eng.asp?id=392582
关键词：
Development generalized perturbation theory model

项目摘要

The main objective of this research proposal consists of developing a procedure that can be used to propagate through the code DRAGON the uncertainties in basic nuclear data. A lattice cell code that includes such uncertainty analysis features will clearly represent a quantum step over the current analysis codes since one will then be able to evaluate the effect of uncertainties in the experimental nuclear data on global reactor operation parameter. The procedures for sensitivity coefficient evaluation we propose to develop will be based on a direct method but also on a Monte Carlo and a more efficient adjoint technique. This later method is based on the generalized perturbation theory (GPT) method already implemented in the code DRAGON. We will also address the problem of deriving a GPT approach to evaluate the sensitivity coefficients associated with the resonance self-shielding model programmed in DRAGON. Finally, a new cross section library that includes covariance matrices will be defined and implemented in DRAGON. This work will lead to improvements in the quality and versatility of the analysis tools that are used for reactor physics calculations in such a way that they can also satisfy the analysis needs of the next generations of reactors (Advanced CANDU and Generation IV). The fact that the errors limits in the precision of the core power distributions due to errors in the cross sections can be evaluated using these tools should reduce substantially the level of arbitrariness in reactor safety studies.

该研究建议的主要目的是开发一种程序，该程序可用于通过代码龙传播基本核数据中的不确定性。包含此类不确定性分析特征的晶格单元格代码将显然代表当前分析代码上的量子步骤，因为人们将能够评估不确定性在实验核数据中对全局反应器操作参数的影响。我们提出的敏感性系数评估程序将基于直接方法，也基于蒙特卡洛和更有效的伴随技术。以后的方法基于代码龙已经实现的广义扰动理论（GPT）方法。我们还将解决得出GPT方法的问题，以评估与在Dragon中编程的共振自屏模型相关的灵敏度系数。最后，将在Dragon中定义和实现一个包括协方差矩阵的新的横截面库。这项工作将改善用于反应堆物理计算的分析工具的质量和多功能性，以使它们还可以满足下一代反应堆（高级CANDU和IV代）的分析需求。由于横截面中的错误，可以使用这些工具评估核心功率分布精确的错误限制，这一事实应大大降低反应堆安全研究中的任意性水平。