Steady-state analyses of an smDFR with coupled Serpent-OpenFOAM calculation
Steady-state analyses of an smDFR with coupled Serpent-OpenFOAM calculation
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通过耦合 Serpent-OpenFOAM 计算对 smDFR 进行稳态分析
DOI：
10.1016/j.nucengdes.2022.111892
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发表时间：
2022-09
影响因子：
1.7
通讯作者：
Xiang Wang
中科院分区：
文献类型：
--
作者：
Songyang Liu;Tian Zhang;Xiang Wang
·验证了蒙特卡罗程序Serpent 2和CFD程序OpenFOAM通过Python接口的耦合代码，并将其应用于smDFR。结果表明，与非耦合余弦形功率分布相比，燃料和冷却剂的温度分布更加准确。·更好地代表了smDFR，为今后的设计和分析提供了重要参考。小型模块化双流体反应堆(SmDFR)采用液态铀和氯化钚的混合物作为燃料，以铅作为冷却剂。SMDFR具有体积小、重量轻、固有安全性好的特点，可作为车船的移动能源。对SMDFR的分析还处于早期阶段，基于单个或单独的物理场，很难捕捉到流动的燃料对中子场的影响。为了获得稳定的smDFR堆芯性能的多维、多场分布，需要进行中子流耦合动力学计算。在这项工作中，蒙特卡罗程序Serpent 2和CFD程序OpenFOAM通过一个Python接口耦合，从而可以以区域平均的方式与流体场交换中子场信息。以压水堆为背景，用两个算例验证了耦合程序的正确性和可靠性，计算结果吻合较好。将该耦合程序应用于SMDFR、单通道和1/6核壳的稳态分析。结果表明，燃料和冷却液的温度分布导致轴向功率峰值漂移小于非耦合余弦形功率分布。1/6堆芯实验结果表明，堆芯顶部中心处燃料的峰值温度达到980K。此外，还研究了额定功率下燃料热物性和进气速度的影响。通过对映射方案的比较，可以识别出具体参数的依赖关系，有助于减少映射误差。这项工作表明，通过中子场-CFD耦合程序，可以更好地表示smDFR的多维和多物理场，为今后smDFR系统的设计和分析提供重要的参考。
• A coupling code for the Monte Carlo code Serpent 2 and the CFD code OpenFOAM via a Python interface is verified and applied for the smDFR. • The results show more accurate temperature distribution of the fuel and coolant compared to the uncoupled cosine shape power distribution. • The smDFR is better represented, providing important references for the future design and analyses. The small modular dual fluid reactor (smDFR) adopts a mixture of liquid uranium and plutonium chloride as fuel, with lead as a coolant. With its smaller size, lower weight, and inherent safety, the smDFR can be used as a mobile energy supply for vehicles or ships. Analyses of the smDFR are still in the early stage based on a single or separated physical field, which can hardly capture the impact of the flowing fuel on the neutron field. The coupled neutronic-fluid dynamic calculation is needed for reliable multidimensional, multi-field distribution of the steady-state smDFR core property. In this work, the Monte Carlo code Serpent 2 and the CFD code OpenFOAM are coupled via a Python interface, whereby the neutron field information can be exchanged with the fluid field in a region-average manner. The correctness and reliability of the coupled code are verified with two cases in the pressurized water reactor background, and the results show good agreement. The coupled code is applied to the steady-state analyses of an smDFR, a single-channel case, and a 1/6-core case. The results show that the temperature distribution of the fuel and coolant caused a lower drift of the axial power peak compared to the uncoupled cosine shape power distribution. The 1/6-core results show that the peak temperature of the fuel reaches 980 K at the top-center of the reactor core. Moreover, the influence of fuel thermal properties and inlet velocity are studied with rated power. Through the comparison of mapping schemes, the results can identify the dependence of specific parameters and help to reduce mapping errors. This work shows that through a coupled neutronic-CFD code, the multidimensional and multi-physical fields of the smDFR can be better represented, providing important references for the future design and analyses of smDFR systems.
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影响因子：
4.7
作者：
Manuele Au fi ero;A. Cammi;Olivier Geoffroy;M. Losa;L. Luzzi;M. Ricotti;Hervé Rouch
通讯作者：
Manuele Au fi ero;A. Cammi;Olivier Geoffroy;M. Losa;L. Luzzi;M. Ricotti;Hervé Rouch
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影响因子：
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作者：
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通讯作者：
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影响因子：
1.9
作者：
Louhanrong Yu;Lei Wang;Chao Liu;Bin Wu;Jing Song;Yican Wu
通讯作者：
Louhanrong Yu;Lei Wang;Chao Liu;Bin Wu;Jing Song;Yican Wu
影响因子：
2.8
作者：
通讯作者：
--
DOI：
--
发表时间：
2017
期刊：
--
影响因子：
--
作者：
Xiang Wang
通讯作者：
Xiang Wang