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Considerations of Scaling Effects in the LOFT Reactor System During a Large Break LOCA Simulation
An investigation was performed to assess the effects of scale in a reduced-scale integral test facility designed to simulate the response of a commercial four-loop pressurized water reactor (PWR) during a hypothesized loss-of-coolant accident (LOCA). The facility considered in the investigation was the Loss-of-Fluid Test (LOFT) system, which simulates the principal physical features of a PWR, but has only one-fiftieth of the fluid volume. LOFT experimental data and data from comparable Semiscale Mod-1 and Mod-3 tests were used to assess the influences of component scaling characteristics on LOFT performance during a 200% cold leg break LOCA simulation. (ERA citation 04:040944)
Considerations of Scaling Effects in the LOFT Reactor System During a Large Break LOCA Simulation
An investigation was performed to assess the effects of scale in a reduced-scale integral test facility designed to simulate the response of a commercial four-loop pressurized water reactor (PWR) during a hypothesized loss-of-coolant accident (LOCA). The facility considered in the investigation was the Loss-of-Fluid Test (LOFT) system, which simulates the principal physical features of a PWR, but has only one-fiftieth of the fluid volume. LOFT experimental data and data from comparable Semiscale Mod-1 and Mod-3 tests were used to assess the influences of component scaling characteristics on LOFT performance during a 200% cold leg break LOCA simulation. (ERA citation 04:040944)
Considerations of Scaling Effects in the LOFT Reactor System During a Large Break LOCA Simulation
M. A. Langerman (Autor:in) / E. A. Harvego (Autor:in)
1979
4 pages
Report
Keine Angabe
Englisch
LOFT LOCA: WHAM6 Model and Code Application
NTIS | 1978
|NTIS | 1985
|NTIS | 1979
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