CFETR COOL包层热-机械性能研究

蒋科成; 余毅; 马学斌; 陈磊; 刘松林

doi:10.13832/j.jnpe.2023.S1.0101

CFETR COOL包层热-机械性能研究

doi: 10.13832/j.jnpe.2023.S1.0101

蒋科成^1,,
余毅^{1, 2},
马学斌¹,
陈磊¹,
刘松林¹

1.
中国科学院合肥物质科学研究院，等离子体物理研究所，合肥，230031
2.
中国科学技术大学，合肥，230026

基金项目: 国家自然科学基金项目(12205330)

详细信息

作者简介:
蒋科成（1993—），男，副研究员，现主要从事聚变堆包层设计及性能分析方面的研究，E-mail: jiangkecheng@ipp.ac.cn

中图分类号: TL334
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- 被引次数: 0
出版历程
- 收稿日期: 2023-02-19
- 修回日期: 2023-06-12
- 刊出日期: 2023-06-15

Thermal-mechanic Analysis on COOL Blanket for CFETR

1.
Institute of Plasma Physics, Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei, 230031, China
2.
University of Science and Technology of China, Hefei, 230026, China

摘要

摘要: 超临界二氧化碳（sCO₂）液态锂铅包层（COOL）是中国聚变工程实验堆（CFETR）的候选包层，其主要功能是增殖产氚、屏蔽中子辐射以及能量转换发电。COOL包层在正常运行工况下需要承受冷却剂压力、热应力、重力、电磁力等载荷。本文在不考虑重力和电磁载荷的情况下，采用ANSYS有限元方法对COOL包层扇段的赤道面外包层模块进行热-机械性能分析，结果表明，COOL包层在正常运行工况下，各类材料的最高温度不超过限值，并且结构应力能够满足ITER SDC-IC设计标准，分析结果可为包层优化设计提供重要参考和数据支撑。
- 中国聚变工程实验堆(CFETR) /
- 超临界二氧化碳(sCO₂)液态锂铅包层(COOL) /
- 热-机械性能
Abstract: The supercritical carbon dioxide (sCO₂) liquid lead-lithium blanket (COOL) is a candidate for China Fusion Engineering Test Reactor (CFETR), and its main functions are tritium breeding, neutron radiation shielding and energy conversion to generate electricity. COOL cladding needs to bear loads such as coolant pressure, thermal stress, gravity and electromagnetic force under normal operating conditions. In this paper, the thermal and mechanical performance of the equatorial outboard blanket module in the COOL blanket segment are analyzed by ANSYS finite element method. The results show that the maximum temperature of various materials of the blanket under normal operating condition does not exceed the upper limit, and the structural stress could meet the ITER SDC-IC design standard. The analysis results can provide important reference and data support for the following iterative optimal design of the blanket.
- CFETR /
- Supercritical carbon dioxide (sCO₂) liquid lead-lithium blanket (COOL) /
- Thermal-mechanical properties

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图 1 CFETR及包层扇段模型

Figure 1. CFETR and Blanket Segment Model

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图 2 COOL包层香蕉型设计

Figure 2. Banana Shaped Design of COOL Blanket

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图 3 核热密度沿径向分布

Figure 3. Radial Distribution of Nuclear Thermal Density

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图 4 赤道面外包层模块网格划分

Figure 4. Mesh Arrangement for Equatorial Outboard Blanket Module

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图 5 各结构部件温度场

Figure 5. Temperature Field of Structural Components

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图 6 各结构部件应力场

Figure 6. Stress Field of Structural Components

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表 1 COOL包层热分析边界条件

Table 1. Boundary Conditions for Thermal Analysis of COOL Blanket

部件	冷却剂主流温度/℃	对流换热系数/[W·(m²·K)⁻¹]
第一壁	375	7636
冷却板	375	2062
径向支撑板	375	4808
进口联箱	350	4222
出口联箱	400	4339
第一排锂铅通道	577 ~ 661	845
第二排锂铅通道	509 ~ 546	613
第三排锂铅通道	484 ~ 503	488

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表 2 包层各部件最高温度汇总

Table 2. Summary of Maximum Temperatures for Different Components in Blanket

部件	最高温度/℃	温度限值/℃
钨铠甲	513.8	< 1300
碳化硅插件	573.5	< 1000
碳化钨	368.0	< 1495
第一壁	506.2	< 550
冷却板	450.1
径向支撑板	490.6
联箱	438.7
间隙-第一壁	423.8	< 480
间隙-冷却板	450.1
间隙-径向支撑板	490.6
间隙-联箱	438.7

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表 3 不同温度下RAFM钢的许用应力强度

Table 3. Allowable Stress Strength of RAFM Steel at Different Temperatures

温度/℃	300	350	400	450	500	550
S_m /MPa	177	172	165	154	139	118

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表 4 正常运行工况下包层结构部件一次应力分析结果

Table 4. Primary Stress Analysis Results for Blanket Structural Components under Normal Operating Conditions

部件	$ \overline {{P_{\text{m}}}} $/MPa	S_m /MPa	S_m裕度/%	$ \overline {{P_{\text{L}}} + {P_{\text{b}}}} $ /MPa	1.5 S_m/MPa	1.5 S_m裕度/%
第一壁	70.8	170.2	58.4	102.5	255.4	59.9
冷却板	82.0	166.0	50.6	118.0	249.1	52.6
径向支撑板	131.3	170.8	23.1	195.4	256.3	23.8
联箱	90.81	171.2	47.0	100.0	256.8	61.1

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表 5 正常运行工况下包层热-机械性能分析结果

Table 5. Thermal-mechanical Analysis Results for Blanket under Normal Operating Conditions

部件	$ {\text{Max}}(\overline {{P_{\text{L}}} + {P_{\text{b}}}} ) + \overline Q $ /MPa	3S_m /MPa	3S_m裕度/%
第一壁	280.3	498.9	43.8
冷却板	359.9	496.7	27.5
径向支撑板	483.8	497.1	2.7
联箱	597.9	498.6	-19.9

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