A Porous Media Model for Thermal-hydraulic Analysis of Wire-wrapped Fuel Assembly in Sodium Cooled Fast Reactor

Wang Xinan; Zhang Dalin; Wang Ting; Qiu Suizheng; Su Guanghui

doi:10.13832/j.jnpe.2024.02.0147

Volume 45 Issue 2

Apr. 2024

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Wang Xinan, Zhang Dalin, Wang Ting, Qiu Suizheng, Su Guanghui. A Porous Media Model for Thermal-hydraulic Analysis of Wire-wrapped Fuel Assembly in Sodium Cooled Fast Reactor[J]. Nuclear Power Engineering, 2024, 45(2): 147-153. doi: 10.13832/j.jnpe.2024.02.0147

Citation:

Wang Xinan, Zhang Dalin, Wang Ting, Qiu Suizheng, Su Guanghui. A Porous Media Model for Thermal-hydraulic Analysis of Wire-wrapped Fuel Assembly in Sodium Cooled Fast Reactor[J]. Nuclear Power Engineering, 2024, 45(2): 147-153. doi: 10.13832/j.jnpe.2024.02.0147

Citation:

Wang Xinan, Zhang Dalin, Wang Ting, Qiu Suizheng, Su Guanghui. A Porous Media Model for Thermal-hydraulic Analysis of Wire-wrapped Fuel Assembly in Sodium Cooled Fast Reactor[J]. Nuclear Power Engineering, 2024, 45(2): 147-153. doi: 10.13832/j.jnpe.2024.02.0147

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A Porous Media Model for Thermal-hydraulic Analysis of Wire-wrapped Fuel Assembly in Sodium Cooled Fast Reactor

doi: 10.13832/j.jnpe.2024.02.0147

1.
China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen, Guangdong, 518000, China
2.
State Key Laboratory of Multiphase Flow in Power Engineering, Xi’an Jiaotong University, Xi’an, 710049, China

Received Date: 2023-04-14
Rev Recd Date: 2023-11-09
Publish Date: 2024-04-12

Abstract

Abstract

In order to accurately predict the distribution of three-dimensional thermal-hydraulic parameters in the core of sodium-cooled fast reactor and reduce the demand for computing resources, a three-dimensional porous medium model for the wire-wrapped fuel assembly was established based on the concept of representative element volume. The interaction between the coolant and the solid surface is decomposed into distributed resistance force according to the geometry characteristics of the assembly. An effective heat transfer coefficient model including turbulent mixing heat transfer, fluid heat transfer and fuel rod heat transfer was introduced to describe the radial heat transfer of the assembly. Numerical analysis was performed for the liquid sodium cooled 37-pin wire wrapped fuel assembly experiment conducted by the Nuclear Energy Engineering Laboratory of Toshiba Corporation. Compared with the experimental results, the numerical calculation results show that the porous medium model proposed in this paper can well reproduce the experimental results under various conditions. Therefore, the porous medium model proposed in this study can be used to predict the distribution of three-dimensional thermal-hydraulic parameters of the wire-wrapped fuel assembly of sodium-cooled fast reactor.
- Sodium cooled fast reactor,
- Wire-wrapped fuel assembly,
- Representative element volume,
- Porous medium model

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References(18)

References

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