Thermal Hydro-Mechanical Analysis of Reactor Vessel Cooling System under Station Blackout Accident

QIAO Xue-dong; YANG Hong-yi; FENG Yu-heng

Volume 27 Issue S1

Jun. 2006

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QIAO Xue-dong, YANG Hong-yi, FENG Yu-heng. Thermal Hydro-Mechanical Analysis of Reactor Vessel Cooling System under Station Blackout Accident[J]. Nuclear Power Engineering, 2006, 27(S1): 1-4,22.

Citation:

QIAO Xue-dong, YANG Hong-yi, FENG Yu-heng. Thermal Hydro-Mechanical Analysis of Reactor Vessel Cooling System under Station Blackout Accident[J]. Nuclear Power Engineering, 2006, 27(S1): 1-4,22.

QIAO Xue-dong, YANG Hong-yi, FENG Yu-heng. Thermal Hydro-Mechanical Analysis of Reactor Vessel Cooling System under Station Blackout Accident[J]. Nuclear Power Engineering, 2006, 27(S1): 1-4,22.

Citation:

QIAO Xue-dong, YANG Hong-yi, FENG Yu-heng. Thermal Hydro-Mechanical Analysis of Reactor Vessel Cooling System under Station Blackout Accident[J]. Nuclear Power Engineering, 2006, 27(S1): 1-4,22.

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Thermal Hydro-Mechanical Analysis of Reactor Vessel Cooling System under Station Blackout Accident

China Institute of Atomic Energy, Beijing, 102413, China

Received Date: 2005-11-05
Rev Recd Date: 2006-01-16

Available Online: 2025-07-23

Publish Date: 2006-06-15

Abstract

Abstract

Reactor vessel cooling system is one of the important auxiliary systems in the primary system of China experimental fast reactor（CEFR）,which can cool the reactor vessel in various conditions.the reactor cooling system during the station blackout accident.It provides the data for the mechanical analysis,and the theoretical support to the optimum design and safety analysis of the fast reactors.
- Blackout accident,
- Natural circulation,
- Transient,
- Temperature field