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Verification of multiphysics coupling techniques for modeling of molten salt reactors
Annals of Nuclear Energy ( IF 1.9 ) Pub Date : 2021-07-31 , DOI: 10.1016/j.anucene.2021.108578
J. Groth-Jensen 1 , A. Nalbandyan 1 , E.B. Klinkby 1 , B. Lauritzen 1 , P. Sabbagh 2 , A.V. Pedersen 3
Affiliation  

Crucial to the development of molten salt reactor (MSR) designs is the application of multiphysics codes to model the tightly coupled neutronics and thermal-hydraulics behaviour of the liquid fuel. However, the verification and validation of such codes is not a trivial task, in particular for fast reactor designs, where no experimental data are available. In absence of experimental data, a benchmark was developed by LPSC/CNRS-Grenoble for multiphysics codes dedicated to MSR studies. In this study we present two independent multiphysics approaches and apply them to this benchmark. The first approach utilizes the Serpent2 multiphysics interface, allowing for high fidelity coupling of the finite volume computational fluid dynamics code OpenFOAM and Serpent2. In this approach, Serpent2 serves as the neutronics solver and is coupled to an OpenFOAM based thermal-hydraulics solver and supplemented by a delayed neutron precursors transport solver implemented in OpenFOAM. The main advantage of this coupling approach is that it allows for using a high accuracy Monte-Carlo approach to solve the neutron transport equations. The second approach is a novel approach that utilizes the SEALION framework. The SEALION code employs a specialized thermal hydraulics solver based on OpenFOAM, coupled with a custom-made modified point kinetics neutronics solver, that explicitly accounts for the altered neutron importance due to the transport of delayed neutron precursors. The main advantage of this approach is that it allows for a pre-determination of the temperature feedback effects using Monte-Carlo codes, such as Serpent2. Both approaches are verified against results from the benchmark and the overall agreement between the results demonstrates the validity of both approaches.



中文翻译:

熔盐反应堆建模的多物理场耦合技术验证

熔盐反应堆 (MSR) 设计发展的关键是应用多物理场代码来模拟液体燃料的紧密耦合中子学和热工水力行为。然而,此类代码的验证和确认并非易事,特别是对于没有实验数据可用的快堆设计。在缺乏实验数据的情况下,LPSC/CNRS-Grenoble 为专用于 MSR 研究的多物理场代码开发了一个基准。在这项研究中,我们提出了两种独立的多物理场方法并将它们应用于该基准。第一种方法利用 Serpent2 多物理场接口,允许有限体积计算流体动力学代码 OpenFOAM 和 Serpent2 的高保真耦合。在这种方法中,Serpent2 用作中子学求解器,并与基于 OpenFOAM 的热工水力求解器耦合,并辅以在 OpenFOAM 中实现的延迟中子前体传输求解器。这种耦合方法的主要优点是它允许使用高精度蒙特卡罗方法来求解中子输运方程。第二种方法是一种利用 SEALION 框架的新颖方法。SEALION 代码采用基于 OpenFOAM 的专门热液压求解器,并结合定制的修改点动力学中子学求解器,该求解器明确解释了由于延迟中子前体的传输而改变的中子重要性。这种方法的主要优点是它允许使用蒙特卡罗代码(例如 Serpent2)预先确定温度反馈效应。

更新日期:2021-08-01
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