Analysis of Primary Loop Small-Break Loss-of-Coolant Accident

HUANG Hongwen; LIU Hangang; QIAN Dazhi; XU Xianqi

Volume 31 Issue 4

Aug. 2010

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HUANG Hongwen, LIU Hangang, QIAN Dazhi, XU Xianqi. Analysis of Primary Loop Small-Break Loss-of-Coolant Accident[J]. Nuclear Power Engineering, 2010, 31(4): 78-81.

Citation:

HUANG Hongwen, LIU Hangang, QIAN Dazhi, XU Xianqi. Analysis of Primary Loop Small-Break Loss-of-Coolant Accident[J]. Nuclear Power Engineering, 2010, 31(4): 78-81.

HUANG Hongwen, LIU Hangang, QIAN Dazhi, XU Xianqi. Analysis of Primary Loop Small-Break Loss-of-Coolant Accident[J]. Nuclear Power Engineering, 2010, 31(4): 78-81.

Citation:

HUANG Hongwen, LIU Hangang, QIAN Dazhi, XU Xianqi. Analysis of Primary Loop Small-Break Loss-of-Coolant Accident[J]. Nuclear Power Engineering, 2010, 31(4): 78-81.

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Analysis of Primary Loop Small-Break Loss-of-Coolant Accident

Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang, Sichuan, 621900, China

Received Date: 2009-02-15
Rev Recd Date: 2009-08-21
Publish Date: 2010-08-01

Abstract

Abstract

On the basis of a typical model of the primary loop small-break loss-of-coolant accident,the transient variation of the thermo hydraulics parameters at a loss-of-coolant accident are calculated by RETRAN-02 code.The physical process and the relevant measures for protection under the incident condition are analyzed.The calculation result shows that the reactor has a favorable capacity to resist the accident.
- Small-break loss-of-coolant accident,
- RETRAN-02,
- Thermal hydraulics