Abstract
One of the design aspects to improve reactor safety is the integration of the steam generator of pressurized water reactor (PWR) and other components including pressurizer into pressure vessel. By utilizing a movable boundary spatial discretization technique and choosing suitable heat transfer correlation, the physical mathematical model and calculating code to predicate the thermo-hydraulic behavior of once-through steam generator were established. The calculating results are in good agreement with the experimental data.
| Original language | English |
|---|---|
| Pages (from-to) | 413-418 |
| Number of pages | 6 |
| Journal | Hedongli Gongcheng/Nuclear Power Engineering |
| Volume | 19 |
| Issue number | 5 |
| State | Published - 1998 |
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