Safety Characteristics Analysis of Helium-Xenon Cooled Reactor System under LOCA

Liao Haoyang; Ming Yang; Zhao Fulong; Lu Ruibo; Wei Ruixuan; Gao Puzhen; Tan Sichao; Tian Ruifeng

doi:10.13832/j.jnpe.2024.06.0197

Volume 45 Issue 6

Dec. 2024

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Article Navigation > Nuclear Power Engineering > 2024 > 45(6): 197-205

Liao Haoyang, Ming Yang, Zhao Fulong, Lu Ruibo, Wei Ruixuan, Gao Puzhen, Tan Sichao, Tian Ruifeng. Safety Characteristics Analysis of Helium-Xenon Cooled Reactor System under LOCA[J]. Nuclear Power Engineering, 2024, 45(6): 197-205. doi: 10.13832/j.jnpe.2024.06.0197

Citation:

Liao Haoyang, Ming Yang, Zhao Fulong, Lu Ruibo, Wei Ruixuan, Gao Puzhen, Tan Sichao, Tian Ruifeng. Safety Characteristics Analysis of Helium-Xenon Cooled Reactor System under LOCA[J]. Nuclear Power Engineering, 2024, 45(6): 197-205. doi: 10.13832/j.jnpe.2024.06.0197

Citation:

Liao Haoyang, Ming Yang, Zhao Fulong, Lu Ruibo, Wei Ruixuan, Gao Puzhen, Tan Sichao, Tian Ruifeng. Safety Characteristics Analysis of Helium-Xenon Cooled Reactor System under LOCA[J]. Nuclear Power Engineering, 2024, 45(6): 197-205. doi: 10.13832/j.jnpe.2024.06.0197

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Safety Characteristics Analysis of Helium-Xenon Cooled Reactor System under LOCA

doi: 10.13832/j.jnpe.2024.06.0197

Liao Haoyang^{1, 2
,},
Ming Yang^{1, 2},
Zhao Fulong^{1, 2
,
,},
Lu Ruibo³,
Wei Ruixuan^{1, 2},
Gao Puzhen^{1, 2},
Tan Sichao^{1, 2},
Tian Ruifeng^{1, 2}

1.
College of Nuclear Science and Technology, Harbin Engineering University, Harbin, 150001, China
2.
Heilongjiang Key Laboratory of Nuclear Power Plant Performance and Equipment, Harbin Engineering University, Harbin, 150001, China
3.
Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2023-10-16
Rev Recd Date: 2024-02-23
Publish Date: 2024-12-17

Abstract

Abstract

In order to avoid the high risk and harm caused by the loss of coolant accident (LOCA) in the reactor system, the developed LOCA analysis code for helium-xenon cooled reactor system was used to simulate a variety of LOCA transient conditions, and the system transient characteristics, volume filling influence characteristics, load following failure influence characteristics, break location influence characteristics and break size influence characteristics were analyzed. The results show that the system pressure and mass flow rate decrease rapidly after the LOCA. Volume filling can alleviate LOCA, reducing the rate of mass flow rate decline and the rate of reactor outlet temperature rise by 77.15% and 90.27%, respectively. Both the constant load and the break at high pressure have a negative impact on LOCA, resulting in an increase in the rate of mass flow rate decline by 13.85% and 79.83% respectively, and an increase in the rate of reactor outlet temperature rise by 15.84% and 96.06% respectively. The decrease rates of system pressure and mass flow rate rise with the increase of the break size. Especially between 15 mm and 30 mm of the break size, the flow rate decreases and the reactor outlet temperature increases significantly by 258.84% and 595.91%, respectively.
- Direct Brayton cycle,
- Helium-xenon gas mixture,
- Loss of coolant accident (LOCA),
- System simulation code

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References(14)

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