Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysis
Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysis
复制标题
DOI：
10.1016/j.ces.2014.03.003
复制
发表时间：
2014-05
影响因子：
4.7
通讯作者：
Manuele Au fi ero;A. Cammi;Olivier Geoffroy;M. Losa;L. Luzzi;M. Ricotti;Hervé Rouch
中科院分区：
文献类型：
--
作者：
Manuele Au fi ero;A. Cammi;Olivier Geoffroy;M. Losa;L. Luzzi;M. Ricotti;Hervé Rouch
本文讨论了非慢化熔盐堆瞬态分析的多物理场模型的建立。特别注意描述了所采用的时间积分和物理耦合策略。该模型采用隐式龙格-库塔格式，并将中子扩散方程、reynolds -平均Navier-Stokes质量和动量守恒方程、能量和延迟中子前体平衡方程耦合在一起，以准确捕捉中子的热反馈。求解器旨在执行全堆芯三维熔盐快堆几何结构的快速运行模拟。根据蒙特卡罗模拟评估了中子模型，并将简化案例研究的结果与先前开发的多物理场工具的结果进行了比较。作为模型能力的一个例子，模拟和讨论了一个无保护的MSFR单泵故障事故场景。该模型的主要目的是为燃料回路部件设计优化阶段提供快速运行的计算工具。总的来说，它对循环燃料系统的反应堆物理研究有重要的帮助。
In the paper, the development of a multiphysics model for the transient analysis of non-moderated Molten Salt Reactors is discussed. Particular attention is devoted to the description of the adopted time integration and physics coupling strategies. The proposed model features the adoption of an implicit Runge–Kutta scheme and the coupling among neutron diffusion, Reynolds-Averaged Navier–Stokes equations for mass and momentum conservation, and energy and delayed neutron precursor balance equations, in order to accurately catch thermal feedbacks on neutronics. The solver is aimed at performing fast-running simulations of the full-core three-dimensional Molten Salt Fast Reactor geometry. The neutronics modelling is assessed against Monte Carlo simulations and the results of a simplified case study are compared to those from multiphysics tools previously developed. As an example of the capability of the model, an unprotected MSFR single pump failure accidental scenario is simulated and discussed. The main purpose of the present model is to serve as fast-running computational tool in the phase of design optimization of fuel loop components. More in general, it is of valuable help in the study of reactor physics of circulating-fuel systems.