Compact intermediate heat transport system for sodium cooled reactor
AssigneeGeneral Electric Company
InventorsCharles E. Boardman, John P. Maurer
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AssigneeGeneral Electric Company
InventorsCharles E. Boardman, John P. Maurer
Estimating the term…
An intermediate heat transport system is disclosed for providing steam generation from the secondary nonradioactive liquid sodium heat extraction loop from a sodium cooled nuclear reactor. The transport system includes a unitary module combining the steam generating heat exchanger, the pump for the circulation of the liquid sodium coolant, and the surge volume required for differential expansion between the sodium and the vessels that contain the sodium. Two concentric cylindrical and vertically standing vessels are provided for containing the liquid sodium; one vessel is outer and larger; the other inner vessel is of a double wall construction and open on its lower end hung from the top of the longer vessel. The outer and larger cylindrical vessel has four feedwater inlet plenums (typical number) at the bottom and four steam outlet plenums at the top. Tube sheets terminate each plenum to a tube bundle extending between the inlet and outlet plenums. At least one electromagnetic high temperature sodium pump is placed within the inner vessel and hermetically sealed for pumping sodium to and from the reactor, this pump acting in the preferred capacity as the jet of a jet pump for pumping the sodium.
In combination with a sodium cooled reactor having an intermediate heat exchanger for extracting heat in a nonradioactive secondary sodium loop from said sodium reactor, the combination including:
Dependencies are inferred from the claim text.