Analysis of Effect of Hydraulic Characteristic of Reactor Coolant Pump on Large-Break Loss-of-Coolant Accident

DING Shuhua; QIAN Libo; WU Dan

Mar. 2025

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DING Shuhua, QIAN Libo, WU Dan. Analysis of Effect of Hydraulic Characteristic of Reactor Coolant Pump on Large-Break Loss-of-Coolant Accident[J]. Nuclear Power Engineering, 2013, 34(S1): 192-195.

Citation:

DING Shuhua, QIAN Libo, WU Dan. Analysis of Effect of Hydraulic Characteristic of Reactor Coolant Pump on Large-Break Loss-of-Coolant Accident[J]. Nuclear Power Engineering, 2013, 34(S1): 192-195.

DING Shuhua, QIAN Libo, WU Dan. Analysis of Effect of Hydraulic Characteristic of Reactor Coolant Pump on Large-Break Loss-of-Coolant Accident[J]. Nuclear Power Engineering, 2013, 34(S1): 192-195.

Citation:

DING Shuhua, QIAN Libo, WU Dan. Analysis of Effect of Hydraulic Characteristic of Reactor Coolant Pump on Large-Break Loss-of-Coolant Accident[J]. Nuclear Power Engineering, 2013, 34(S1): 192-195.

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Analysis of Effect of Hydraulic Characteristic of Reactor Coolant Pump on Large-Break Loss-of-Coolant Accident

National Key Laboratory of Reactor System Design Technology, Nuclear Power Institute of China, Chengdu, 610041, China

Received Date: 2013-04-01
Rev Recd Date: 2013-05-10

Available Online: 2025-03-08

Abstract

Abstract

The best estimate code WCOBRA/TRAC was utilized to model AP1000 Large-Break Loss-of-Coolant Accident.The effect of four different types of pump characteristics curves on the system pressure,break mass flow rate and peak clad temperature was analyzed.It was found that for LB LOCA accident,the difference on the peak clad temperature during the blow-down and the reflooding phase could be up to 150℃ with different pump curves.The safety margin of AP1000 could be improved through optimizing or improving the pump characteristics.
- Pump characteristics curve,
- Large-break loss-of-coolant accident,
- AP1000