IP Library Granted Patent US 12674576
Granted Patent B2
US 12674576 · App. 17/991,837 · Granted Jul 7, 2026

Stress relieving attachment of tube to tubesheet, such as in a pressure vessel shell of a nuclear reactor power system

Inventors: Tamas R. Liszkai (Corvallis, OR); Todd Sorensen (St Joseph, MI)
Assignee: NuScale Power, LLC
F22B37/002G21C1/322
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Quick Facts
Patent No.
US 12674576
App. No.
17/991,837
Granted
Jul 7, 2026
Kind
B2
Abstract

Steam generator systems including tubesheet assemblies, such as for use in nuclear reactor systems, and associated devices and methods are described herein. A representative steam generator system can be installed in a nuclear reactor vessel positioned to house a primary coolant. The steam generator system can include a tubesheet assembly defining a plenum and comprising a tubesheet and a flexible connection portion coupling the tubesheet to the reactor vessel. The tubesheet can include a plurality of perforations fluidly coupled to the plenum. The steam generator system can further comprise a plurality of heat transfer tubes fluidly coupled to the perforations and configured to receive a flow of a secondary coolant. The connection portion can be more flexible than the tubesheet and the reactor vessel to reduce stresses on the tubesheet and the connections (e.g., tube-to-tubesheet (TTS) welds) between the tubes and the tubesheet during operation of the nuclear reactor system.

Claims (17)

1 . A steam generator system for use in a nuclear reactor system including a reactor vessel positioned to house a primary coolant, the steam generator system comprising:

a tubesheet assembly coupled to the reactor vessel, forming at least a portion of a plenum, and comprising—

a tubesheet including a plurality of perforations fluidly coupled to the plenum, wherein the reactor vessel extends along a longitudinal axis, and wherein the tubesheet is inclined relative to the longitudinal axis by an angle of between about 15°-45°; and

a connection portion at least partially between the tubesheet and the reactor vessel, wherein the connection portion is more flexible than the tubesheet and the reactor vessel; and

a plurality of heat transfer tubes configured to receive a flow of a secondary coolant, wherein individual ones of the heat transfer tubes are fluidly coupled to corresponding ones of the perforations.

2 . The steam generator system of claim 1 wherein the tubesheet is a flat plate, and wherein the tubesheet assembly includes a groove extending circumferentially about the tubesheet and defining the connection portion.

3 . The steam generator system of claim 2 wherein the tubesheet includes an inner surface positioned to face an interior of the reactor vessel and an outer surface positioned to face the plenum, and wherein the groove extends partially from the outer surface toward the inner surface.

4 . The steam generator system of claim 2 wherein the flat plate has a circular shape, and wherein the groove has a circular shape with a generally constant width and depth.

5 . The steam generator system of claim 2 wherein the groove has a width that varies in a circumferential direction.

6 . The steam generator system of claim 1 wherein the tubesheet assembly is integrally formed with the reactor vessel.

7 . The steam generator system of claim 1 wherein the tubesheet is a flat plate having an inner surface positioned to face an interior of the reactor vessel and an outer surface positioned to face the plenum, wherein the tubesheet assembly includes a first groove extending circumferentially about the tubesheet from the inner surface partially toward the outer surface and a second groove extending circumferentially about the tubesheet from the outer surface partially toward the inner surface, and wherein the first groove and the second groove define the connection portion.

8 . The steam generator system of claim 1 wherein the tubesheet has a first thickness, and wherein the connection portion has a second thickness less than the first thickness.

9 . The steam generator system of claim 8 wherein the first thickness is less than half the second thickness.

10 . The steam generator system of claim 1 wherein the tubesheet assembly further comprises an inlet port fluidly coupled to the plenum, and wherein the tubesheet assembly is positioned to receive the secondary coolant in liquid form via the inlet port and route the secondary coolant in liquid form through the plenum into the perforations and into the heat transfer tubes.

11 . The steam generator system of claim 1 wherein the tubesheet assembly further comprises an outlet port fluidly coupled to the plenum, and wherein the tubesheet assembly is positioned to receive the secondary coolant in vapor form from the heat transfer tubes and route the secondary coolant in vapor form through the perforations into the plenum and into the outlet port.

12 . The steam generator system of claim 1 wherein the primary coolant is positioned to absorb heat from a nuclear reaction within the reactor core.

13 . The steam generator system of claim 1 wherein the secondary coolant is configured to absorb heat from the primary coolant through the plurality of heat transfer tubes.