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U.S. Department of Energy
Office of Scientific and Technical Information

Pressurized-water coolant nuclear reactor steam generator

Patent ·
OSTI ID:4089268
A description is given of a pressurized-water coolant nuclear reactor steam generator having a vertical housing for the steam generating water and containing an upstanding heat exchanger to which the pressurized-water coolant passes and which is radially surrounded by a guide jacket supporting a water separator on its top. By thermosiphon action the steam generating water flows upward through and around the heat exchanger within the guide chamber to the latter's top from which it flows radially outwardly and downwardly through a down draft space formed between the outside of the jacket and the housing. The water separator discharges separated water downwardly. The housing has a feedwater inlet opening adjacent to the lower portion of the heat exchanger, providing preheating of the introduced feedwater. This preheated feedwater is conveyed by a duct upwardly to a location where it mixes with the water discharged from the water separator. (Official Gazette)
Research Organization:
Originating Research Org. not identified
NSA Number:
NSA-33-019441
Assignee:
to Siemens Aktiengesellschaft
Patent Number(s):
US 3921591
OSTI ID:
4089268
Country of Publication:
United States
Language:
English