Pump behavior and its impact on a loss-of-coolant accident in a pressurized water reactor
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:5624263
The impact of a loss-of-coolant accident (LOCA) on a nuclear reactor is determined in its first phase by many events, one of them being the behavior of the reactor coolant pumps. In this case, a mixture of steam and water flows through the pumps. Experiments were carried out to examine the family of characteristics of geometrically scaled pumps (scale 1:5 and 1:4) within the relevant parameter range under such conditions. The presented results of steady-state experiments are compared with results of former projects. Besides flow and speed, the most significant parameters on two-phase pump performance are void fraction and system pressure. A brief comparison between steady-state and transient results is provided. The impact of the pump's behavior on the LOCA is demonstrated on the basis of blowdown calculations using various pump models and two-phase pump data.
- Research Organization:
- Kraftwerk Union AG, KWU/R 153, Postfach 3220 Hammerbacherstrasse 12 and 14, 8520 Erlangen
- OSTI ID:
- 5624263
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 60:2; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
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ACCIDENTS
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REACTOR ACCIDENTS
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TRANSIENTS
TWO-PHASE FLOW
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VOID FRACTION
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WATER COOLED REACTORS
WATER MODERATED REACTORS