Abstract
A PWR Reactivity Insertion Accidents (RIA) analysis capability, based on the three-dimensional coupled thermal-hydraulic/neutronics code TRAC-PF1/NEM, has been developed. Several verification and validation studies were conducted showing that TRAC-PF1/NEM is qualified for RIA applications. The applications of TRAC-PF1/NEM to Rod Ejection Accident and the Main Steam Line Break transient analyses to upgrade the power of the TMI-1 NPP were also conducted. In these applications, TRAC-PF1/NEM was used with the Studsvik of America CASMO-3/SIMULATE-3 code package.
Original language | English (US) |
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Pages | 183-184 |
Number of pages | 2 |
State | Published - 1997 |
Event | Proceedings of the 1997 5th International Conference on Nuclear Engineering, ICONE5 - Nice, Fr Duration: May 25 1997 → May 29 1997 |
Other
Other | Proceedings of the 1997 5th International Conference on Nuclear Engineering, ICONE5 |
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City | Nice, Fr |
Period | 5/25/97 → 5/29/97 |
All Science Journal Classification (ASJC) codes
- Nuclear Energy and Engineering