Locating hot and cold-legs in a nuclear powered steam generation system
- Delmont, PA
- New Kensington, PA
A nuclear reactor steam generator includes a reactor vessel for heating water and a steam generator with a pump casing at the lowest point on the steam generator. A cold-leg pipe extends horizontally between the steam generator and the reactor vessel to return water from the steam generator to the reactor vessel. The bottom of the cold-leg pipe is at a first height above the bottom of the reactor vessel. A hot-leg pipe with one end connected to the steam generator and a second end connected to the reactor vessel has a first pipe region extending downwardly from the steam generator to a location between the steam generator and the reactor vessel at which a bottom of the hot-leg pipe is at a second height above the bottom of the reactor vessel. A second region extends from that location in a horizontal direction at the second height to the point at which the hot-leg pipe connects to the reactor vessel. A pump is attached to the casing at a location below the first and second heights and returns water from the steam generator to the reactor vessel over the cold-leg. The first height is greater than the second height and the bottom of the steam generator is at a height above the bottom of the reactor vessel that is greater than the first and second heights. A residual heat recovery pump is below the hot-leg and has an inlet line from the hot-leg that slopes down continuously to the pump inlet.
- Research Organization:
- Westinghouse Electric Corp., Pittsburgh, PA (United States)
- DOE Contract Number:
- AC03-90SF18495
- Assignee:
- Westinghouse Electric Corp. (Pittsburgh, PA)
- Patent Number(s):
- US 5263067
- OSTI ID:
- 869023
- Country of Publication:
- United States
- Language:
- English
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