Steam generator for a nuclear reactor

Patent metadata

Field	Value
Publication number	US-10147507-B2
Application number	US-201414567487-A
Country	US
Kind code	B2
Filing date	Dec 11, 2014
Priority date	Apr 20, 2012
Publication date	Dec 4, 2018
Grant date	Dec 4, 2018

Abstract

A steam generator for a nuclear reactor comprises plenums proximate with a first plane, wherein the first plane intersects a bottom portion of a riser column of a reactor vessel. The steam generator may further comprise plenums proximate with a second plane, approximately parallel with the first plane, wherein the second plane intersects a top portion of the riser column of the reactor vessel. The steam generator may further include a plurality of steam generator tubes that convey coolant from a plenum located proximate with the first plane to one of the plenums proximate with the second plane.

First claim

What is claimed is:

1. A method of operating a nuclear reactor steam generator, comprising:
conveying a working fluid from a first group of plenums to a plurality of flowpaths, each of the plenums having an approximately flat tubesheet with a plurality of perforations, wherein a number of the plurality of perforations per unit of area of the approximately flat tubesheet changes between an area of the approximately flat tubesheet near an inner edge of the at least one plenum and an area near an outer edge of the at least one plenum, the conveying further comprising conveying the working fluid to the plurality of flowpaths through the plurality of perforations;
vaporizing the working fluid in at least some of the plurality of flowpaths, the vaporizing resulting, at least in part, from transferring thermal energy from a reactor coolant to the at least some of the plurality of flowpaths; and
transferring the vaporized coolant to a second group of plenums.

2. The method of claim 1 , wherein the conveying further comprises reducing pressure of the working fluid.

3. The method of claim 2 , wherein the working fluid is reduced in pressure by an amount of at least 15.0% of an overall pressure drop resulting, at least in part, from a flowpath extending between a first plenum of the first group of plenums located at a first plane and a second plenum of the second group of plenums located at a second plane.

4. The method of claim 1 , wherein transferring further comprises transferring the working fluid to the second group of plenums through an approximately flat tubesheet of each plenum of the second group of plenums.

5. The method of claim 1 , wherein the flowpaths extend helically between the first group of plenums and the second group of plenums.

6. The method of claim 4 , wherein the transferring further comprises transferring the working fluid to the second group of plenums through a plurality of perforations in the approximately flat tubesheet of at least one plenum of the second group of plenums.

7. A method of operating a nuclear reactor steam generator, comprising:
conveying a working fluid from a first set of a plurality of chambers to a plurality of tubes, wherein the chambers of the first set of chambers are disposed around a riser column;
vaporizing the working fluid in at least some of the plurality of tubes, the vaporizing resulting, at least in part, from transferring thermal energy from a reactor coolant to the at least some of the plurality of tubes; and
transferring the vaporized coolant from the plurality of tubes to a second set of a plurality of chambers, wherein chambers of the second set of chambers are disposed around the riser column;
wherein the pressure of the working fluid is reduced by an amount of at least 15.0% of an overall pressure drop resulting, at least in part, from a tube extending between a first chamber of the first set of chambers located at a first height and a second plenum of the second set of chambers located at a second height.

8. The method of claim 7 , wherein the conveying further comprises reducing a pressure of the working fluid.

9. The method of claim 7 , wherein the conveying further comprises conveying the working fluid to the plurality of tubes through an approximately flat tubesheet of each chamber of the first set of chambers.

10. The method of claim 7 , wherein transferring further comprises transferring the working fluid to the second set of chambers through an approximately flat tubesheet of each chamber of the second set of chambers.

11. The method of claim 7 , wherein the tubes extend helically between the first set of chambers and the second set of chambers.

12. The method of claim 9 , wherein the coupling further comprises conveying the working fluid to the plurality of tubes through a plurality of perforations in the approximately flat tubesheet of each chamber of the first set of chambers.

13. The method of claim 10 , wherein the transferring further comprises transferring the working fluid to the second set of chambers through a plurality of perforations in the approximately flat tubesheet of each chamber of the second set of chambers.

14. The method of claim 12 , wherein a number of the plurality of perforations per unit of area of the approximately flat tubesheet changes between an area of the approximately flat tubesheet near an inner edge of the at least one chamber and an area near an outer edge of the at least one chamber.

15. A method of operating a nuclear reactor steam generator, comprising:
conveying a working fluid from a first group of plenums into an internal portion of a plurality of flowpaths, wherein the plenums of the first group of plenums are disposed around a riser column at a first height, each of the plenums having an approximately flat tubesheet with a plurality of perforations, wherein a number of the plurality of perforations per unit of area of the approximately flat tubesheet changes between an area of the approximately flat tubesheet near an inner edge of the at least one plenum and an area near an outer edge of the at least one plenum;
conveying a reactor coolant from the riser column along an external portion of the plurality of flowpaths, wherein the reactor coolant is conveyed from a second height to the first height;
vaporizing the working fluid in at least some of the plurality of flowpaths, the vaporizing resulting, at least in part, from transferring thermal energy from the reactor coolant to the at least some of the plurality of flowpaths; and
transferring the vaporized coolant from the plurality of flowpaths to a second group of plenums, wherein the plenums of the second group of plenums are disposed around the riser column at the second height.

Assignees

• Nuscale Power Llc

Inventors

• Groome John T
• Joh Sooyun
• Nylander James Allan

Classifications

• F22B1/162 Primary

  in combination with a nuclear installation · CPC title

• G21C15/16 Primary

  comprising means for separating liquid and steam (separating in general B01D; steam traps F16D) · CPC title

• G21C15/14

  from headers; from joints in ducts · CPC title

• G21D1/006

  primary side of steam generators (secondary side of steam generators F22B1/00, F22B35/00 or F22B37/00) · CPC title

• G21C15/12

  from pressure vessel; from containment vessel · CPC title