Method Study and Application for Neutronics Optimization of Solid Tritium Breeding Blanket of Fusion Reactor
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摘要: 为提升聚变堆包层产氚性能，更好地满足氚自持要求，首先，基于中子微扰理论与模拟退火算法开发了适用于聚变堆产氚包层（TBB）中子学优化新算法与新程序。其次，选取中国聚变工程实验堆（CFETR）氦冷固态包层，完成了全堆中子学性能优化的示范性应用。最后，对优化后的包层方案进行了热工、流体、结构的三维有限元校核。结果表明：①相比于传统包层中子学优化算法，本文所提出的优化算法具有更好的优化效果与更高的优化效率；②本文所开发的智能优化程序可更好地满足聚变堆TBB中子学优化与设计的需求，可为包层设计提供算法理论基础与程序支撑。Abstract: This paper aims to improve the tritium breeding performance of the Tritium Breeding Blanket (TBB) of fusion reactors to better meet the tritium self-sufficiency. First, based on neutronics perturbation theory and simulated annealing algorithm, a new algorithm and program for neutronics optimization of TBB are developed. Second, the helium cooled solid blanket of China Fusion Engineering Test Reactor（CFETR） is selected to complete the demonstration application of the whole reactor neutronics performance optimization. Finally, the 3D finite element check of thermal, fluid and structure is carried out for the optimized blanket scheme. The results show that: ① The optimization algorithm proposed in this paper has better optimization effect and higher optimization efficiency than the traditional blanket neutronics optimization algorithm; ② The intelligent optimization program developed in this paper can better meet the needs of neutronics optimization and design of the fusion reactor blanket, and provide the theoretical basis of algorithm and program support for the blanket design.
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图 1 聚变堆TBB中子学优化创新流程
Figure 1. Innovative Process for Neutronics Optimization of Fusion Reactor TBB
图 5 CFETR HCCB TBB 22.5°扇区中子学模型（左）与CAD反转模型（右）
Figure 5. Neutronics Model of 22.5° Sector of CFETR Helium Cooled Solid TBB (Left) and CAD Inversion Model (Right)
图 7 CFETR HCCB TBB模块内部氚增殖区TBR分布
Figure 7. TBR Distribution in Internal Breeding Zone of CFETR HCCB TBB Module
表 1 组合优化问题与TBB的TBR优化问题的相似性
Table 1. Similarities between Combinatorial Optimization and TBR Optimization of TBB
组合优化过程 聚变堆TBB的TBR优化问题 解 包层设计方案 目标函数 TBR 最优解 TBR下的包层设计方案 设定初始温度 设定退火初始温度 抽样过程 随机产生新方案 控制参数的下降 降温 
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表 2 各典型CFETR HCCB TBB 模块增殖区径向厚度
Table 2. Radial Thickness of Each Breeding Zone of Each CFETR HCCB TBB Module
增殖区编号 径向厚度/cm #1~#4模块 #5模块 #6模块 #7模块 #8~#11模块 Li-1 1.4 1.4 1.5 1.6 1.1 Be-1 1.6 1.6 5.5 4.1 2.7 Li-2 1.6 1.6 1.6 1.9 1.7 Be-2 2.8 2.8 6.1 6.6 2.8 Li-3 1.7 1.7 2.7 3.1 2.0 Be-3 3.9 3.9 9.5 2.4 4.8 Li-4 1.8 1.8 5.6 — 2.2 Be-4 5.8 5.8 — — 7.0 Li-5 2.3 2.3 — — 3.0 Be-5 11.1 11.1 — — 3.7 Li-6 3.9 4.8 — — — Be-6 13.1 — — — — “—”表示不存在此区域的几何数据
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表 3 优化后各典型包层模块增殖区径向厚度
Table 3. Radial Thickness of Breeding Zone of Each Typical Blanket Module after Optimization
增殖区编号 径向厚度/cm #1~#4模块 #5模块 #6模块 #7模块 #8~#11模块 Li-1 1.1 1.3 1.2 1.4 1.3 Be-1 1.8 1.8 4.8 2.0 2.2 Li-2 1.1 1.0 1.4 1.5 1.1 Be-2 2.8 2.8 6.8 5.0 3.2 Li-3 1.0 1.0 1.0 3.4 1.3 Be-3 5.1 4.7 13.5 6.4 5.6 Li-4 1.5 1.6 3.8 — 1.6 Be-4 7.3 7.4 — — 7.8 Li-5 2.4 1.6 — — 2.4 Be-5 11.3 12.2 — — 4.5 Li-6 4.2 3.4 — — — Be-6 11.4 — — — — “—”表示不存在此区域的几何数据
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表 4 CFETR氦冷包层各典型模块中子壁负载
Table 4. Neutron Wall Loading of Each Typical Module in CFETR Helium Cooled Blanket
包层模块编号 NWL/(MW·m−2) #1 1.00 #2 1.33 #3 1.69 #4 1.51 #5 1.23 #6 0.87 #7 0.64 #8 0.58 #9 1.17 #10 1.09 #11 0.52
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表 5 CFETR氦冷包层各个典型模块热工校核计算结果
Table 5. Calculation Results of Thermal Check of Each Typical Module in CFETR Helium Cooled Blanket
包层模
块编号ODS钢温度/K Li4SiO4温度/K Be温度/K 最高温度 许用温度 最高温度 许用温度 最高温度 许用温度 1 910 923 1145 1173 911 923 2 914 923 1096 1173 919 923 3 894 923 1151 1173 918 923 4 879 923 1120 1173 921 923 5 895 923 1020 1173 920 923 6 918 923 1160 1173 921 923 7 901 923 1120 1173 918 923 9 891 923 1106 1173 903 923
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