Experimental and Numerical Simulation Study on Pressure Suppression Characteristics of Small PWR

Qiu Zhifang; Guo Rongda; Cao Xuewu; Yu Hongxing; Sun Hongping; Luo Yuejian

doi:10.13832/j.jnpe.2023.01.0060

Volume 44 Issue 1

Feb. 2023

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2023 > 44(1): 60-66

Qiu Zhifang, Guo Rongda, Cao Xuewu, Yu Hongxing, Sun Hongping, Luo Yuejian. Experimental and Numerical Simulation Study on Pressure Suppression Characteristics of Small PWR[J]. Nuclear Power Engineering, 2023, 44(1): 60-66. doi: 10.13832/j.jnpe.2023.01.0060

Citation:

Qiu Zhifang, Guo Rongda, Cao Xuewu, Yu Hongxing, Sun Hongping, Luo Yuejian. Experimental and Numerical Simulation Study on Pressure Suppression Characteristics of Small PWR[J]. Nuclear Power Engineering, 2023, 44(1): 60-66. doi: 10.13832/j.jnpe.2023.01.0060

Citation:

Qiu Zhifang, Guo Rongda, Cao Xuewu, Yu Hongxing, Sun Hongping, Luo Yuejian. Experimental and Numerical Simulation Study on Pressure Suppression Characteristics of Small PWR[J]. Nuclear Power Engineering, 2023, 44(1): 60-66. doi: 10.13832/j.jnpe.2023.01.0060

PDF( 11245 KB)

Experimental and Numerical Simulation Study on Pressure Suppression Characteristics of Small PWR

doi: 10.13832/j.jnpe.2023.01.0060

1.
Shanghai Jiao Tong University, Shanghai, 200240, China
2.
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2022-02-18
Rev Recd Date: 2022-04-04
Publish Date: 2023-02-15

Abstract

Abstract

In order to study the pressure suppression effect of suppression system of small PWR, a small containment pressure suppression characteristic test device is established. Constant flow mixed gas emission test and variable flow mixed gas emission test are carried out to study the influence of gas-water volume ratio and non-condensable gas on the pressure suppression effect. The experimental result results show that when the gas-water volume ratio is in the range of 2~4.55, the pressure suppression effect gradually increases with the increase of the gas-water volume ratio; The content of non-condensable gas in the mixed gas has a significant influence on the pressure suppression effect. The numerical simulation of the experiment is carried out, and the simulation results can reflect the phenomenon law of the pressure suppression test, but the pressure suppression condensation model still needs to be further optimized to improve the simulation accuracy.
- Small PWR,
- Small containment,
- Suppression characteristics,
- Experimental study,
- Numerical simulation

FullText(HTML)

References(12)

References

[1]	MEIER M. Numerical and experimental study of large steam-air bubbles injected in a water pool[D]. Swiss: Swiss Federal Institute of Technology, 1999.
[2]	A Group of Experts of the NEA/CSNI. Pressure suppression system containments: a state-of-the-art report[R]. Paris: Committee on the Safety of Nuclear Installations OECD Nuclear Energy Agency, 1986.
[3]	BROSCHE D. A model for the calculation of vent clearing transients in pressure suppression systems[J]. Nuclear Engineering and Design, 1976, 38(1): 131-141.
[4]	MOODY F J. Dynamic and thermal behavior of hot gas bubbles discharged into water[J]. Nuclear Engineering and Design, 1986, 95: 47-54.
[5]	NORMAN T L. Steam-air mixture condensation in a subcooled water pool[D]. West Lafayette: Purdue University, 2007.
[6]	GAMBLE R E, NGUYEN T N, SHIRALKAR B S, et al. Pressure suppression pool mixing in passive advanced BWR plants[J]. Nuclear Engineering and Design, 2001, 204(1-3): 321-336. doi: 10.1016/S0029-5493(00)00363-0
[7]	KLJENAK I, MAVKO B. Simulation of containment thermal-hydraulics in the Marviken Blowdown 16 experiment with ASTEC and CONTAIN codes[J]. Nuclear Engineering and Design, 2011, 241(4): 1063-1070. doi: 10.1016/j.nucengdes.2010.06.015
[8]	PUUSTINEN M, LAINE J, RÄSÄNE A. PPOOLEX experiments on thermal stratification and mixing: NKS-198[R]. Roskilde: Nordisk Kernesikkerhedsforskning, 2009.
[9]	陈耀峰,王升飞,方圆,等. LOCA下小型抑压式安全壳内流动与传热现象初步研究[J]. 核科学与工程,2021, 41(2): 402-409. doi: 10.3969/j.issn.0258-0918.2021.02.028
[10]	郭景新,郭张鹏,蔡孝玉,等. 基于正交试验的抑压水池抑压特性研究[J]. 核科学与工程,2021, 41(4): 838-843. doi: 10.3969/j.issn.0258-0918.2021.04.024
[11]	蒋孝蔚,邓坚,余红星,等. 小型压水堆安全壳抑压传热研究[J]. 核动力工程,2018, 39(S1): 66-69. doi: 10.13832/j.jnpe.2018.S1.0066
[12]	BERNA C, ESCRIVÁ A, MUÑOZ-COBO J L, et al. Enhancement of the SPARC90 code to pool scrubbing events under jet injection regime[J]. Nuclear Engineering and Design, 2016, 300: 563-577. doi: 10.1016/j.nucengdes.2016.02.027