Pressurized water reactor
US-9251919-B2 · Feb 2, 2016 · US
US10403407B2 · US · B2
| Field | Value |
|---|---|
| Publication number | US-10403407-B2 |
| Application number | US-201414182985-A |
| Country | US |
| Kind code | B2 |
| Filing date | Feb 18, 2014 |
| Priority date | Dec 31, 2013 |
| Publication date | Sep 3, 2019 |
| Grant date | Sep 3, 2019 |
A practical reading order for non-experts. Skip the full description unless you need deep technical detail.
What the patent document calls the invention.
A short plain-language summary of the technical disclosure.
Who owns or filed the patent and who is credited as inventor.
Filing, priority, publication, and grant dates set the timeline.
The legal scope of protection — read this for what is actually claimed.
Technology tags used to group this patent with similar filings.
Prior art links and similar publications in this corpus.
Official abstract text for this publication.
A nuclear reactor seismic isolation assembly includes an enclosure that defines a volume; a plastically-deformable member mounted, at least in part, within the volume; and a stretching member moveable within the enclosure to plastically-deform the plastically-deformable member in response to a dynamic force exerted on the enclosure.
Opening claim text (preview).
What is claimed is: 1. A nuclear reactor seismic isolation assembly, comprising: an enclosure that defines a volume; a plastically-deformable member mounted, at least in part, within the volume; and a stretching member movable within the enclosure, wherein the stretching member is mounted within a bore that extends at least partially through the plastically-deformable member, wherein a first portion of the bore comprises a first diameter substantially equal to an outer dimension of the stretching member, the bore comprising another portion that comprises a second diameter smaller than the first diameter, wherein the stretching member is configured to plastically-deform the plastically-deformable member when the stretching member moves further into the bore in response to a dynamic force exerted on the enclosure, and wherein the second diameter is stretched to substantially equal the first diameter based on linear movement of the stretching member through the bore in response to the dynamic force exerted on the enclosure. 2. The nuclear reactor seismic isolation assembly of claim 1 , wherein the plastically-deformable member comprises a first portion mounted within the enclosure and a second portion that extends through a die member to an exterior of the enclosure. 3. The nuclear reactor seismic isolation assembly of claim 2 , wherein the second portion is welded to a reactor bay embedment. 4. The nuclear reactor seismic isolation assembly of claim 2 , wherein the die member is movable with the stretching member in response to the dynamic force exerted on the enclosure. 5. The nuclear reactor seismic isolation assembly of claim 1 , wherein the bore at least partially encloses a working fluid that dissipates at least a portion of energy generated by the dynamic force exerted on the enclosure based on movement of the stretching member through the bore in response to the dynamic force exerted on the enclosure. 6. The nuclear reactor seismic isolation assembly of claim 1 , further comprising a fluid passage that fluidly couples the bore to the exterior of the enclosure. 7. The nuclear reactor seismic isolation assembly of claim 6 , wherein the working fluid comprises a portion of a fluid enclosed in a nuclear reactor bay. 8. The nuclear reactor seismic isolation assembly of claim 1 , wherein the enclosure is attachable to a portion of a nuclear reactor containment vessel. 9. A nuclear reactor system, comprising: a reactor bay that encloses a liquid; a nuclear reactor containment vessel that is mounted within the reactor bay with lugs positioned in embedments of the reactor bay; and seismic isolation assemblies mounted in the embedments and between the lugs and walls of the embedments, each of the seismic isolation assemblies comprising: an enclosure that defines a volume; a plastically-deformable member mounted, at least in part, within the volume; and a stretching member moveable within the enclosure to plastically-deform the plastically-deformable member in response to a dynamic force exerted on the reactor bay, wherein the stretching member is mounted within a bore that extends at least partially through the plastically-deformable member, and wherein the stretching member is configured to plastically-deform the plastically-deformable member when the stretching member moves further into the bore in response to the dynamic force exerted on the enclosure, and wherein the plastic deformation of the plastically-deformable member results, at least in part, from a linear movement of the stretching member into the bore, and wherein the plastic deformation of the plastically-deformable member occurs in a substantially transverse direction to the linear movement of the stretching member into the bore. 10. The nuclear reactor system of claim 9 , wherein the plastically-deformable member comprises a first portion mounted within the enclosure and a second portion that extends through a die member to a wall of one of the embedments. 11. The nuclear reactor system of claim 10 , wherein the second portion is anchored to the wall. 12. The nuclear reactor system of claim 10 , wherein the die member is movable with the stretching member in response to the dynamic force exerted on the reactor bay. 13. The nuclear reactor system of claim 9 , wherein a first portion of the bore comprises a first diameter approximately equal to an outer dimension of the stretching member, the bore comprising another portion that comprises a second diameter smaller than the first diameter. 14. The nuclear reactor system of claim 13 , wherein the second diameter is stretched to approximately equal the first diameter based on the movement of the stretching member thought the bore in response to the dynamic force exerted on the reactor bay. 15. The nuclear reactor system of claim 9 , wherein the bore at least partially encloses a working fluid that dissipates at least a portion of energy generated by the dynamic force exerted on the enclosure based on movement of the stretching member through the bore in response to the dynamic force exerted on the reactor bay. 16. The nuclear reactor system of claim 9 , further comprising a fluid passage that fluidly couples the bore to a volume defined by the reactor bay. 17. The nuclear reactor system of claim 16 , wherein the working fluid comprises a portion of a fluid enclosed in the volume. 18. The nuclear reactor system of claim 9 , wherein the dynamic force comprises a seismically generated force. 19. An apparatus, comprising: an enclosure configured to receive a force from a nuclear reactor pressure vessel, wherein the force is generated, at least in part, by a seismic event; stretching means at least partially housed within the enclosure; means for transmitting the force to the stretching means, wherein the stretching means is configured to move within the enclosure in response to the force; and means for dissipating at least a portion of the received force based on a plastic deformation of the means for dissipating, wherein the stretching means is mounted within a bore that extends at least partially through the means for dissipating, wherein the plastic deformation of the means for dissipating results, at least in part, from a linear movement of the stretching means further into the bore, and wherein the plastic deformation of the means for dissipating occurs in a substantially transverse direction to the linear movement of the stretching means. 20. The apparatus of claim 19 , wherein friction is generated between the means for dissipating and the stretching means based, at least in part, on repeated movement of the stretching means into the means for dissipating in response to the force, wherein the means for dissipating comprises means for dissipating another portion of the force based on the generated friction. 21. The apparatus of claim 19 , further comprising means for compressing a working fluid enclosed in a chamber of the means for dissipating based on movement of the stretching means into the means for dissipating based on the force. 22. The apparatus of claim 21 , further comprising means for expelling the working fluid to a reactor bay that encloses a liquid, and through a fluid passageway that fluidly couples the chamber and the reactor bay. 23. The apparatus of claim 22 , wherein another portion of the received force is dissipated through the liquid enclosed in the reactor bay. 24. The apparatus of claim 19 , furthe
Arrangements for expansion and contraction · CPC title
Safety arrangements (emergency protection of reactor G21C9/00) · CPC title
Details of nuclear power plant (control G21D3/00) · CPC title
Means for suppressing fires {; Earthquake protection} · CPC title
Joints between tubes and vessel walls, e.g. taking into account thermal stresses · CPC title
Related publications grouped by family.
Answers are generated from the same data shown on this page.