Abstract The evaluation of hot channel factor (HCF) is of great significance to the quantification of safety margins for reactor designs. In this paper, HCFs for a sodium-cooled fast reactor (SFR) are evaluated with the Simulation-based High-efficiency Advanced Reactor Prototyping (SHARP) toolkit, which is developed under the Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign of DOE for multi-physics reactor performance and safety simulations. The high-fidelity neutronics and thermal hydraulics solvers PROTEUS and Nek5000 in the SHARP toolkit are coupled to perform the multi-physics simulations for HCF evaluation. The HCFs induced by cladding manufacturing tolerance, fissile content mal-distribution, wire orientation and uncertainties on the cladding, coolant, and fuel properties are evaluated for a reference core SFR design (AFR-100). The HCFs calculated with the SHARP toolkit are compared to legacy HCFs for similar reactor types. The comparison demonstrates the reduction or elimination of modeling uncertainties in the calculation of HCFs using high fidelity advanced modeling and simulation tools without the need of expensive experiments. Moreover, the reduction of the uncertainties on HCFs evaluation allows an increase in nominal parameters and safety margin, which in turn improves the economic competitiveness of the SFR.

中文翻译：

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用多物理场工具包评估钠冷快堆热通道系数

摘要 热通道系数（HCF）的评估对于反应堆设计安全裕度的量化具有重要意义。在本文中，钠冷快堆 (SFR) 的 HCF 使用基于模拟的高效先进反应堆原型 (SHARP) 工具包进行评估，该工具包是在美国能源部的核能高级建模和仿真 (NEAMS) 运动下开发的用于多物理场反应堆性能和安全模拟。SHARP 工具包中的高保真中子学和热力水力学求解器 PROTEUS 和 Nek5000 相结合，可以执行多物理场仿真以进行 HCF 评估。由包层制造公差、裂变物含量分布不均、线材方向和包层、冷却剂、和燃料特性针对参考堆芯 SFR 设计 (AFR-100) 进行评估。使用 SHARP 工具包计算的 HCF 与类似反应堆类型的传统 HCF 进行了比较。该比较表明，使用高保真高级建模和仿真工具计算 HCF 时，无需昂贵的实验即可减少或消除建模不确定性。此外，HCF 评估不确定性的减少允许增加名义参数和安全裕度，从而提高 SFR 的经济竞争力。该比较表明使用高保真高级建模和仿真工具计算 HCF 时建模不确定性的减少或消除，而无需进行昂贵的实验。此外，HCF 评估不确定性的减少允许增加名义参数和安全裕度，从而提高 SFR 的经济竞争力。该比较表明使用高保真高级建模和仿真工具计算 HCF 时建模不确定性的减少或消除，而无需进行昂贵的实验。此外，HCF 评估不确定性的减少允许增加名义参数和安全裕度，从而提高 SFR 的经济竞争力。