Investigation of Radial Thermal-Hydraulic Characteristics of Sodium Heated Once-Through Steam Generator

Feng Zhenyu; Liu Yapeng; Wang Bo; Zhang Dalin; Li Xinyu; Tian Wenxi; Qiu Suizheng; Su Guanghui

doi:10.13832/j.jnpe.2025.01.0073

Volume 46 Issue 1

Feb. 2025

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Article Navigation > Nuclear Power Engineering > 2025 > 46(1): 73-82

Feng Zhenyu, Liu Yapeng, Wang Bo, Zhang Dalin, Li Xinyu, Tian Wenxi, Qiu Suizheng, Su Guanghui. Investigation of Radial Thermal-Hydraulic Characteristics of Sodium Heated Once-Through Steam Generator[J]. Nuclear Power Engineering, 2025, 46(1): 73-82. doi: 10.13832/j.jnpe.2025.01.0073

Citation:

Feng Zhenyu, Liu Yapeng, Wang Bo, Zhang Dalin, Li Xinyu, Tian Wenxi, Qiu Suizheng, Su Guanghui. Investigation of Radial Thermal-Hydraulic Characteristics of Sodium Heated Once-Through Steam Generator[J]. Nuclear Power Engineering, 2025, 46(1): 73-82. doi: 10.13832/j.jnpe.2025.01.0073

Citation:

Feng Zhenyu, Liu Yapeng, Wang Bo, Zhang Dalin, Li Xinyu, Tian Wenxi, Qiu Suizheng, Su Guanghui. Investigation of Radial Thermal-Hydraulic Characteristics of Sodium Heated Once-Through Steam Generator[J]. Nuclear Power Engineering, 2025, 46(1): 73-82. doi: 10.13832/j.jnpe.2025.01.0073

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Investigation of Radial Thermal-Hydraulic Characteristics of Sodium Heated Once-Through Steam Generator

doi: 10.13832/j.jnpe.2025.01.0073

1.
School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, 710049, China
2.
Dongfang Electric Co., Ltd., Chengdu, 611731, China

Received Date: 2024-04-25
Rev Recd Date: 2024-07-22
Publish Date: 2025-02-15

Abstract

Abstract

The sodium heated once-through steam generator is the critical equipment of a sodium-cooled fast reactor. The traditional one-dimensional thermal-hydraulic system analysis code cannot take into account the radial thermal-hydraulic parameter distributions of the steam generator, and therefore is not applicable to fatigue and thermal stress analyses. In order to calculate the radial thermal-hydraulic parameter distribution of the steam generator, the TCOSS-2D code was developed adopting a combination of pipe network, pipeline and steam generator. Firstly, radial multilayer modeling and thermal-hydraulic calculations were carried out on the steam generator prototype of the Chinese demonstration fast reactor (CFR600) using TCOSS-2D, and the results showed that the transient response trend calculated by the code was in good agreement with the experiment, so the radial thermal hydraulic calculation capability of the code was validated. Secondly, the radial non-uniform flow distribution on the sodium side of the sodium heated once-through steam generator was considered and compared. The results show that the radial non-uniform sodium-side flow distribution has a greater effect on the radial temperature difference of the evaporator than the superheater, while the non-uniform flow distribution of the sodium-side of the transient process has a relatively small effect on the non-uniformity of the water-side. Therefore, the numerical model of sodium heated once-through steam generator developed in this study can be utilized for the analysis of its radial thermal-hydraulic characteristics.
- TCOSS-2D,
- Sodium heated once-through steam generator,
- Radial thermal-hydraulic,
- Code validation

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References(17)

References

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