G.J. Promey
Research Areas
Nuclear reactor physics and engineering, Nuclear Engineering Thermal-Hydraulics, Heat transfer and supercritical fluids
Most-Cited Works
- → Predictions and measurements of isothermal airflow in a model once-through steam generator(1982)1 cited
- Measurement and THEDA code prediction of thermal, velocity, and pressure fields in a once-through steam generator heated air model. Final report. [PWR](1982)