Design and Analysis of Irradiation Test Scheme for Fast Reactor Fuel Slug with HFETR

Zhang Liang; Yang Wenhua; Zhao Wenbin; Sun Sheng; Jin Shuai; Lei Jin

doi:10.13832/j.jnpe.2022.03.0101

Volume 43 Issue 3

Jun. 2022

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Article Navigation > Nuclear Power Engineering > 2022 > 43(3): 101-106

Zhang Liang, Yang Wenhua, Zhao Wenbin, Sun Sheng, Jin Shuai, Lei Jin. Design and Analysis of Irradiation Test Scheme for Fast Reactor Fuel Slug with HFETR[J]. Nuclear Power Engineering, 2022, 43(3): 101-106. doi: 10.13832/j.jnpe.2022.03.0101

Citation:

Zhang Liang, Yang Wenhua, Zhao Wenbin, Sun Sheng, Jin Shuai, Lei Jin. Design and Analysis of Irradiation Test Scheme for Fast Reactor Fuel Slug with HFETR[J]. Nuclear Power Engineering, 2022, 43(3): 101-106. doi: 10.13832/j.jnpe.2022.03.0101

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Design and Analysis of Irradiation Test Scheme for Fast Reactor Fuel Slug with HFETR

doi: 10.13832/j.jnpe.2022.03.0101

Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2021-04-09
Accepted Date: 2021-12-07
Rev Recd Date: 2021-07-13
Publish Date: 2022-06-07

Abstract

Abstract

Considering the irradiation test index and fuel test safety, the operation requirements of high flux engineering test reactor (HFETR), the pressure difference fluctuation in the test section and other factors, in this paper, based on HFETR, the design and analysis of the fast reactor fuel slug irradiation test plan were carried out, and the key parameters such as the thickness of the lead-bismuth alloy layer, the structure of the cooling water channel, the structure of the thimble plug, and the flow rate of the cooling water were determined, and a high linear power density irradiation test plan with the maximum temperature of the hot rod cladding at (490±60)℃ was obtained. The results show that when the maximum linear power density of the hot rod is 68~85 kW/m, the temperature of the cladding and the fuel core meets the requirements of the irradiation test and has a margin; In the range of 200~300 kPa core pressure difference, the calculated CFX value of the flow in the test section under the same pressure difference is about 9%~11% smaller than the test value; The flow share of the narrow channel outside the test section is 7.3%, which is significantly lower than the flow area share of the channel, meeting the cooling requirements of fuel slugs when the linear power density is 85 kW/m. The irradiation test plan proposed in this paper can provide a reference for the high linear power density irradiation test of fast reactor fuel rods.
- HFETR,
- Fuel irradiation test,
- Fast reactor fuel rod,
- Thermal-hydraulics

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References(10)

References

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