Thermal-mechanic Analysis on COOL Blanket for CFETR

Jiang Kecheng; Yu Yi; Ma Xuebin; Chen Lei; Liu Songlin

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

Volume 44 Issue S1

Jun. 2023

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Article Navigation > Nuclear Power Engineering > 2023 > 44(S1): 101-107

Jiang Kecheng, Yu Yi, Ma Xuebin, Chen Lei, Liu Songlin. Thermal-mechanic Analysis on COOL Blanket for CFETR[J]. Nuclear Power Engineering, 2023, 44(S1): 101-107. doi: 10.13832/j.jnpe.2023.S1.0101

Citation:

Jiang Kecheng, Yu Yi, Ma Xuebin, Chen Lei, Liu Songlin. Thermal-mechanic Analysis on COOL Blanket for CFETR[J]. Nuclear Power Engineering, 2023, 44(S1): 101-107. doi: 10.13832/j.jnpe.2023.S1.0101

Jiang Kecheng, Yu Yi, Ma Xuebin, Chen Lei, Liu Songlin. Thermal-mechanic Analysis on COOL Blanket for CFETR[J]. Nuclear Power Engineering, 2023, 44(S1): 101-107. doi: 10.13832/j.jnpe.2023.S1.0101

Citation:

Jiang Kecheng, Yu Yi, Ma Xuebin, Chen Lei, Liu Songlin. Thermal-mechanic Analysis on COOL Blanket for CFETR[J]. Nuclear Power Engineering, 2023, 44(S1): 101-107. doi: 10.13832/j.jnpe.2023.S1.0101

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Thermal-mechanic Analysis on COOL Blanket for CFETR

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

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

Received Date: 2023-02-19
Rev Recd Date: 2023-06-12
Publish Date: 2023-06-15

Abstract

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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References(17)

References

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