A platform for research: civil engineering, architecture and urbanism
A platform for research: civil engineering, architecture and urbanism
Fuel Rod Response During LOFT Test L2-2
The Loss-of-Fluid Test (LOFT) Facility is providing unique data on the response of a nuclear reactor to a loss-of-coolant accident (LOCA). The data are being used to assess the accuracy of the computer codes used in reactor safety analysis. The first LOFT nuclear test, Test L2-2, was a cold leg break LOCA at a peak linear power of 26.25 kW/m. The paper briefly describes the LOFT core, discusses fuel rod response during Test L2-2, and compares the data with the test prediction. (ERA citation 04:042970)
Fuel Rod Response During LOFT Test L2-2
The Loss-of-Fluid Test (LOFT) Facility is providing unique data on the response of a nuclear reactor to a loss-of-coolant accident (LOCA). The data are being used to assess the accuracy of the computer codes used in reactor safety analysis. The first LOFT nuclear test, Test L2-2, was a cold leg break LOCA at a peak linear power of 26.25 kW/m. The paper briefly describes the LOFT core, discusses fuel rod response during Test L2-2, and compares the data with the test prediction. (ERA citation 04:042970)
Fuel Rod Response During LOFT Test L2-2
D. A. Niebruegge (author) / E. L. Tolman (author)
1979
4 pages
Report
No indication
English