Transient Characteristics Analysis of 2000 kW High Temperature and High Pressure Test Loop of HFETR during Loss of Power Accident of Main Pump

Liu Wenbin; Song Jiyang; Deng Caiyu; Kang Changhu; Xiang Yuxin; Song Yuge; Liu Chang; Guo Yufei; Xing Rujun

doi:10.13832/j.jnpe.2022.03.0074

Volume 43 Issue 3

Jun. 2022

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Article Navigation > Nuclear Power Engineering > 2022 > 43(3): 74-77

Liu Wenbin, Song Jiyang, Deng Caiyu, Kang Changhu, Xiang Yuxin, Song Yuge, Liu Chang, Guo Yufei, Xing Rujun. Transient Characteristics Analysis of 2000 kW High Temperature and High Pressure Test Loop of HFETR during Loss of Power Accident of Main Pump[J]. Nuclear Power Engineering, 2022, 43(3): 74-77. doi: 10.13832/j.jnpe.2022.03.0074

Citation:

Liu Wenbin, Song Jiyang, Deng Caiyu, Kang Changhu, Xiang Yuxin, Song Yuge, Liu Chang, Guo Yufei, Xing Rujun. Transient Characteristics Analysis of 2000 kW High Temperature and High Pressure Test Loop of HFETR during Loss of Power Accident of Main Pump[J]. Nuclear Power Engineering, 2022, 43(3): 74-77. doi: 10.13832/j.jnpe.2022.03.0074

Citation:

Liu Wenbin, Song Jiyang, Deng Caiyu, Kang Changhu, Xiang Yuxin, Song Yuge, Liu Chang, Guo Yufei, Xing Rujun. Transient Characteristics Analysis of 2000 kW High Temperature and High Pressure Test Loop of HFETR during Loss of Power Accident of Main Pump[J]. Nuclear Power Engineering, 2022, 43(3): 74-77. doi: 10.13832/j.jnpe.2022.03.0074

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Transient Characteristics Analysis of 2000 kW High Temperature and High Pressure Test Loop of HFETR during Loss of Power Accident of Main Pump

doi: 10.13832/j.jnpe.2022.03.0074

Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2021-04-15
Accepted Date: 2021-05-26
Rev Recd Date: 2021-09-07
Publish Date: 2022-06-07

Abstract

Abstract

In order to study the safety characteristics of 2000 kW high temperature and high pressure test loop in high flux engineering test reactor (HFETR) in the process of loss of power accident of main pump, the simulation model of test loop is established based on RELAP5 code, and the transient characteristics of loss of power accident of main pump are analyzed by using the verified model. The calculation results show that in the process of loss of power accident of main pump, the high-speed working condition of the main pump switches to the low-speed working condition of the two accident pumps, the flow rate decreases rapidly and finally stabilizes to half of the initial flow rate, and the fuel cladding reaches a peak temperature of 763 K at 4.34 s; Then, due to the continuous decline of power, the cladding temperature decreases continuously; The minimum departure from nucleate boiling ratio during the accident is greater than 1.3, which indicates that departure from nucleate boiling will not occur and meets the safety requirements.
- RELAP5,
- Irradiation test loop,
- Loss of power accident for main pump,
- High flux engineering test reactor (HFETR)

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References(5)

References

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