Steam generator for a nuclear reactor
US-10147507-B2 · Dec 4, 2018 · US
US11062811B2 · US · B2
| Field | Value |
|---|---|
| Publication number | US-11062811-B2 |
| Application number | US-201815945612-A |
| Country | US |
| Kind code | B2 |
| Filing date | Apr 4, 2018 |
| Priority date | Dec 26, 2013 |
| Publication date | Jul 13, 2021 |
| Grant date | Jul 13, 2021 |
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Official abstract text for this publication.
A thermal control system for a reactor pressure vessel comprises a plate having a substantially circular shape that is attached to a wall of the reactor pressure vessel. The plate divides the reactor pressure vessel into an upper reactor pressure vessel region and a lower reactor pressure vessel region. Additionally, the plate is configured to provide a thermal barrier between a pressurized volume located within the upper reactor pressure vessel region and primary coolant located within the lower reactor pressure vessel region. One or more plenums provide a passageway for a plurality of heat transfer tubes to pass fluid through the wall of the reactor pressure vessel. The plurality of heat transfer tubes are connected to the plate.
Opening claim text (preview).
The invention claimed is: 1. A nuclear reactor system comprising: a reactor pressure vessel; a plate attached to a wall of the reactor pressure vessel, wherein the plate at least partially divides the reactor pressure vessel into an upper reactor pressure vessel region and a lower reactor pressure vessel region, and is positioned to re-direct an upward flow of a primary flow exiting a riser within the reactor pressure vessel downwardly in the reactor pressure vessel, and wherein the plate includes at least one orifice configured to controllably allow a primary coolant to pass through the plate between the upper and lower reactor pressure vessel regions, and wherein the plate includes a tubesheet portion; a plurality of heat transfer tubes connected to the plate at the tubesheet portion and extending into the lower reactor pressure vessel region; and a plenum positioned in the upper reactor pressure vessel region, the plenum enclosing the tubesheet region and in fluid communication with an exterior of the reactor pressure vessel to transfer a secondary coolant between the heat transfer tubes and a region outside the reactor pressure vessel. 2. The system of claim 1 , wherein the plurality of heat transfer tubes attach to corresponding through-holes in the tubesheet portion of the plate. 3. The system of claim 2 , wherein the plenum includes a dome extending up from the plate, over the through-holes, and around an opening formed in the wall of the reactor pressure vessel. 4. The system of claim 1 , wherein the at least one orifice is configured to be open or closed, wherein the at least one orifice when open allows the primary coolant to pass through the plate into the upper reactor pressure vessel region, and wherein the at least one orifice when closed prevents the primary coolant from passing through the plate. 5. The system of claim 1 , wherein the plate is welded to a wall of the reactor pressure vessel. 6. The system of claim 1 , wherein the plate comprises: an upper flange mounted to an upper head of the reactor pressure vessel; and a lower flange welded to a lower portion of the reactor pressure vessel. 7. The system of claim 6 , wherein the upper head is spaced apart from the lower portion of the reactor pressure vessel by the upper flange and the lower flange.
from pressure vessel; from containment vessel · CPC title
Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core (G21C1/02 - G21C1/30 take precedence) · CPC title
Energy generation of nuclear origin · CPC title
with heating tubes for nuclear reactors, as long as they are not classified according to a specified heating fluid, in another group · CPC title
Details · CPC title
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