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Analysis of the Influence of Loss of Offsite Power and Moderator Temperature Feedback on the RCP Shaft Seizure Accident of Domestic Advanced PWR
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Bin JIA, Ping-fei DU, Yuan GAO, Xin-li GAO, Xue-dong QIAO, Xin-lu TIAN*
Science Technology and Engineering | 2025, 25(15) : 6344 - 6350
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Science Technology and Engineering | 2025, 25(15): 6344-6350
Papers·Nuclear Technology
Analysis of the Influence of Loss of Offsite Power and Moderator Temperature Feedback on the RCP Shaft Seizure Accident of Domestic Advanced PWR
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Bin JIA, Ping-fei DU, Yuan GAO, Xin-li GAO, Xue-dong QIAO, Xin-lu TIAN*
Affiliations
  • Nuclear and Radiation Safety Center(State Environmental Protection Key Laboratory of Nuclear and Radiation Safety Regulatory Simulation and Validation), Beijing 102488, China
Published: 2025-05-28 doi: 10.12404/j.issn.1671-1815.2406124
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To enhance the support for the nuclear safety review of domestic advanced pressurized water reactor (PWR), the reactor coolant pump (RCP) shaft seizure accident for this reactor type was conducted. The impact of the loss of offsite power (LOOP) assumption and moderator temperature feedback on the accident consequences was examined. The findings are as follows. The peak pressure in the reactor coolant system and the peak temperature of the hot spot cladding, recorded during the accident process, met the accident acceptance criteria, enabling the nuclear power plant to eventually stabilize. The LOOP assumption was found to be conservative. For this accident, however, the differences arising from this assumption manifested in the later stages and did not influence key outcome parameters such as system pressure peak, minimum departure from nucleate boiling ratio (DNBR), and peak temperature of hot spot cladding, which occurred early in the accident. Therefore, the inclusion or exclusion of the LOOP assumption was deemed acceptable. The introduction of moderator temperature feedback was considered an unconservative assumption. Nevertheless, even without this feedback, the peak pressure in the reactor coolant system and the peak temperature of the hot spot cladding still met the accident acceptance criteria, maintaining a substantial margin. Additionally, incorporating moderator temperature feedback brought the calculations closer to reality. Overall, the introduction of moderator temperature feedback in this accident was also judged to be acceptable.

domestic advanced PWR  /  shaft seizure  /  LOOP  /  moderator temperature feedback
Bin JIA, Ping-fei DU, Yuan GAO, Xin-li GAO, Xue-dong QIAO, Xin-lu TIAN. Analysis of the Influence of Loss of Offsite Power and Moderator Temperature Feedback on the RCP Shaft Seizure Accident of Domestic Advanced PWR[J]. Science Technology and Engineering, 2025 , 25 (15) : 6344 -6350 . DOI: 10.12404/j.issn.1671-1815.2406124
Year 2025 volume 25 Issue 15
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doi: 10.12404/j.issn.1671-1815.2406124
  • Receive Date:2024-08-16
  • Online Date:2025-07-09
  • Published:2025-05-28
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  • Received:2024-08-16
  • Revised:2024-11-24
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    Nuclear and Radiation Safety Center(State Environmental Protection Key Laboratory of Nuclear and Radiation Safety Regulatory Simulation and Validation), Beijing 102488, China
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表12种不同金属材料的力学参数

Family
属数
Number of
genus
种数
Number of
species
占总种数比例
Percentage of
total species (%)

Genus
种数
Number of
species
占总种数比例
Percentage of total
species (%)
鹅膏菌科Amanitaceae 2 11 5.26 鹅膏菌属 Amanita 10 4.78
小菇科 Mycenaceae 2 12 5.74 丝盖伞属 Inocybe 5 2.39
多孔菌科 Polyporaceae 8 14 6.70 蜡蘑属 Laccaria 5 2.39
红菇科 Russulaceae 3 23 11.00 小皮伞属 Marasmius 6 2.87
小菇属 Mycena 11 5.26
光柄菇属 Pluteus 5 2.39
红菇属 Russula 17 8.13
栓菌属 Trametes 5 2.39
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