A platform for research: civil engineering, architecture and urbanism
A platform for research: civil engineering, architecture and urbanism
Best Estimate Prediction for LOFT Nuclear Experiment L3-2
Comprehensive analyses using both the RELAP4 and the RELAP5 computer codes were performed to predict the LOFT transient thermal-hydraulic response for nuclear Loss-of-Coolant Experiment L3-2 to be performed in the Loss-of-Fluid Test (LOFT) facility. The LOFT experiment will simulate a small break in one of the cold legs of a large four-loop pressurized water reactor and will be conducted with the LOFT reactor operating at 50 MW. The break in LOCE L3-2 is sized to cause the break flow to be approximately equal to the high-pressure injection system flow at an intermediate pressure of approximately 7.6 MPa. (ERA citation 05:015809)
Best Estimate Prediction for LOFT Nuclear Experiment L3-2
Comprehensive analyses using both the RELAP4 and the RELAP5 computer codes were performed to predict the LOFT transient thermal-hydraulic response for nuclear Loss-of-Coolant Experiment L3-2 to be performed in the Loss-of-Fluid Test (LOFT) facility. The LOFT experiment will simulate a small break in one of the cold legs of a large four-loop pressurized water reactor and will be conducted with the LOFT reactor operating at 50 MW. The break in LOCE L3-2 is sized to cause the break flow to be approximately equal to the high-pressure injection system flow at an intermediate pressure of approximately 7.6 MPa. (ERA citation 05:015809)
Best Estimate Prediction for LOFT Nuclear Experiment L3-2
E. J. Kee (author) / M. S. Shinko (author) / W. H. Grush (author) / K. G. Condie (author)
1980
81 pages
Report
No indication
English
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