Study on Heat Distribution Characteristics of Direct Safety Injection of Reactor Pressure Vessel

Jiang Xing; Weng Yu; Wang Haijun

doi:10.13832/j.jnpe.2021.05.0119

Volume 42 Issue 5

Sep. 2021

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Jiang Xing, Weng Yu, Wang Haijun. Study on Heat Distribution Characteristics of Direct Safety Injection of Reactor Pressure Vessel[J]. Nuclear Power Engineering, 2021, 42(5): 119-122. doi: 10.13832/j.jnpe.2021.05.0119

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Jiang Xing, Weng Yu, Wang Haijun. Study on Heat Distribution Characteristics of Direct Safety Injection of Reactor Pressure Vessel[J]. Nuclear Power Engineering, 2021, 42(5): 119-122. doi: 10.13832/j.jnpe.2021.05.0119

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Study on Heat Distribution Characteristics of Direct Safety Injection of Reactor Pressure Vessel

doi: 10.13832/j.jnpe.2021.05.0119

1.
Shanghai Nuclear Engineering Research and Design Institute Co., Ltd., Shanghai, 200233, China
2.
School of Petroleum Engineering, Xi'an Shiyou University, Xi’an, 710065, China
3.
Xi'an Jiaotong University, Xi’an, 710049, China

Received Date: 2020-08-15
Rev Recd Date: 2020-09-04

Available Online: 2021-09-30

Publish Date: 2021-09-30

Abstract

Abstract

In the passive PWRs in China, the cooling water injection pipe for emergency cooling system is directly connected to the pressure vessel. Unlike the traditional safety injection (SI) of cold leg, this SI mode is called reactor direct SI. For the reactor pressure vessel under the SI conditions, this paper studies the heat distribution shape of the SI fluid on the surface of the pressure vessel by the combination of physical experiment and numerical analysis. As shown in the study, unlike the traditional oblique nozzle SI mode for cold leg of the main pipe, the distribution of SI fluid in the downcomer annulus is approximately in the shape of an isosceles triangle under the direct SI condition. Based on the experimental results and the numerical calculation and verification, the heat distribution angle of the pressure vessel is found directly proportional to the flow rate ratio, and moreover, the calculation model of the SI fluid distribution is proposed for reference in the reactor safety design.
- Reactor pressure vessel,
- Direct SI,
- Visual experiment,
- Numerical calculation,
- Heat distribution

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References(10)

References

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