Managing dynamic forces on a nuclear reactor system

Patent metadata

Field	Value
Publication number	US-2018330833-A1
Application number	US-201816037834-A
Country	US
Kind code	A1
Filing date	Jul 17, 2018
Priority date	Dec 31, 2013
Publication date	Nov 15, 2018
Grant date	—

Abstract

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.

First claim

1 . (canceled)

2 . A nuclear reactor seismic isolation assembly, comprising:
an enclosure that defines a volume; a deformable member mounted, at least in part, within the volume; and a stretching member mounted within a bore that extends at least partially through the deformable member, wherein the stretching member is configured to deform the deformable member in a substantially transverse direction to a linear movement of the stretching member into the bore in response to a dynamic force exerted on the enclosure.

3 . The nuclear reactor seismic isolation assembly of claim 2 , wherein:
a first portion of the bore comprises a first diameter substantially equal to an outer dimension of the stretching member; a second portion of the bore comprises a second diameter smaller than the first diameter; and the second diameter is stretched to substantially equal the first diameter based on the linear movement of the stretching member into the bore.

4 . The nuclear reactor seismic isolation assembly of claim 3 , wherein the 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.

5 . The nuclear reactor seismic isolation assembly of claim 2 , wherein the stretching member deforms an inside surface of the deformable member.

6 . The nuclear reactor seismic isolation assembly of claim 2 , wherein the bore at least partially encloses a fluid that dissipates at least a portion of energy generated by the dynamic force exerted on the enclosure.

7 . The nuclear reactor seismic isolation assembly of claim 6 , further comprising an orifice that fluidly couples the bore to an interior of the enclosure.

8 . The nuclear reactor seismic isolation assembly of claim 6 , wherein the fluid comprises a portion of a fluid enclosed in a nuclear reactor bay.

9 . The nuclear reactor seismic isolation assembly of claim 2 , wherein the enclosure is attachable to a portion of a nuclear reactor containment vessel.

10 . A nuclear reactor system, comprising:
a reactor bay that encloses a liquid; a nuclear reactor containment vessel mounted within the reactor bay with lugs positioned in embedments of the reactor bay; and seismic isolation assemblies mounted in the embedments between the lugs and walls of the embedments, the seismic isolation assemblies comprising: an enclosure that defines a volume; a deformable member with a deformable wall, the deformable member mounted, at least in part, within the volume; and a stretching member moveable within the enclosure to deform the wall of the deformable member in response to a dynamic force exerted on the reactor bay.

11 . The nuclear reactor system of claim 10 , wherein:
the stretching member is mounted within a bore that extends at least partially through the deformable member, and the stretching member is configured to deform the wall of the deformable member when the stretching member moves further into the bore in response to the dynamic force exerted on the enclosure.

12 . The nuclear reactor system of claim 11 , wherein:
the deformation of the deformable member occurs in a substantially transverse direction to a linear movement of the stretching member into the bore.

13 . The nuclear reactor system of claim 11 , wherein the bore comprises:
a first diameter approximately equal to an outer dimension of the stretching member; and 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 though the bore.

15 . The nuclear reactor system of claim 11 , further comprising a fluid passage that fluidly couples the bore to a volume defined by the reactor bay.

16 . The nuclear reactor system of claim 10 , wherein the 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.

17 . The nuclear reactor system of claim 16 , wherein the second portion is anchored to the wall.

18 . 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; a deformable member mounted within an enclosure; and a stretching member configured to move in a linear direction within the deformable member in response to the force and deform the deformable member in a substantially transverse direction to the linear direction of the stretching member.

19 . The apparatus of claim 18 , wherein:
the stretching member is mounted within a bore that extends at least partially through the deformable member, and the stretching member is configured to deform the deformable member in the substantially transverse direction when the stretching member moves into the bore.

20 . The nuclear reactor system of claim 19 , wherein the deformation of the deformable member in the transverse direction causes a portion of the bore into which the stretching member is inserted to increase in diameter.

21 . The apparatus of claim 18 , further comprising one or more spring elements mounted between the enclosure and a reactor bay embedment, wherein the one or more spring elements are configured to dissipate another portion of the received force.

Assignees

• Nuscale Power Llc

Inventors

• Liszkai Tamas

Classifications

• G21D3/04

  Safety arrangements (emergency protection of reactor G21C9/00) · CPC title

• G21C9/00

  Emergency protection arrangements structurally associated with the reactor {, e.g. safety valves provided with pressure equalisation devices}(emergency cooling arrangements G21C15/18) · CPC title

• G21C13/024

  Supporting constructions for pressure vessels or containment vessels · CPC title

• G21C1/32

  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

• G21C13/04

  Arrangements for expansion and contraction · CPC title