Study on SBO Accident and Mitigating Capability of Auxiliary Feedwater System for PWR

ZHANG Long-fei; ZHANG Da-fa; WANG Shao-ming

Sep. 2007

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ZHANG Long-fei, ZHANG Da-fa, WANG Shao-ming. Study on SBO Accident and Mitigating Capability of Auxiliary Feedwater System for PWR[J]. Nuclear Power Engineering, 2007, 28(3): 98-102.

Citation:

ZHANG Long-fei, ZHANG Da-fa, WANG Shao-ming. Study on SBO Accident and Mitigating Capability of Auxiliary Feedwater System for PWR[J]. Nuclear Power Engineering, 2007, 28(3): 98-102.

ZHANG Long-fei, ZHANG Da-fa, WANG Shao-ming. Study on SBO Accident and Mitigating Capability of Auxiliary Feedwater System for PWR[J]. Nuclear Power Engineering, 2007, 28(3): 98-102.

Citation:

ZHANG Long-fei, ZHANG Da-fa, WANG Shao-ming. Study on SBO Accident and Mitigating Capability of Auxiliary Feedwater System for PWR[J]. Nuclear Power Engineering, 2007, 28(3): 98-102.

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Study on SBO Accident and Mitigating Capability of Auxiliary Feedwater System for PWR

Department of Nuclear Science and Engineering, Naval University of Engineering, Wuhan, 430033, China

Received Date: 2006-02-15
Rev Recd Date: 2006-09-20

Available Online: 2025-07-21

Abstract

Abstract

Using the best estimate computer code SCDAP/RELAP5/MOD3.4 and Surry NPP as reference object,a representative three loops PWR severe accident calculation model is established and station blackout（SBO） induced core melt progression and phenomenon is analyzed.Effects are discussed when auxiliary fe-edwater（AFW） operates to mitigate the SBO accident progression 1800s and 3600s after SBO starting.Cal-culation results show that core melt progression and failure time of reactor pressure vessel is greatly delayed,thus the operator has more time available for AC recovery and other mitigation measures to prevent reactor pressure vessel failure.
- Severe accident,
- Station blackout,
- Auxiliary feedwater,
- Creep rupture failure