Nuclear fuel assembly support feature
11404176 · 2022-08-02
Assignee
Inventors
Cpc classification
Y02E30/30
GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
G21C3/3563
PHYSICS
G21C3/33
PHYSICS
International classification
G21C3/33
PHYSICS
Abstract
A nuclear fuel assembly having lateral support provided by a bimetallic spring that extends from a side of the fuel assembly under certain core conditions to pressure against an adjacent component and withdraws under other core conditions, such as shutdown, to enable the nuclear fuel assembly to be aligned or withdrawn from the core and repositioned.
Claims
1. A nuclear fuel assembly having an elongated dimension and comprising: a plurality of interconnected components wherein at least some of the interconnected components comprise: a top nozzle; a bottom nozzle; a plurality of guide thimbles extending between the top nozzle and the bottom nozzle; a plurality of fuel rods extending between the top nozzle and the bottom nozzle; and a plurality of grids arranged in a tandem spaced relationship that extends between the top nozzle and the bottom nozzle along the elongated dimension, with each of the grids having a plurality of cells some of which support fuel rods and others through which the guide thimbles respectively pass and attach to the plurality of grids; wherein at least one grid of the plurality of grids comprises a peripheral surface area that extends in a plane a distance along the elongated dimension; and wherein the at least one grid of the plurality of grids comprises a bimetallic spring that moves between a first and second position relative to the plane as the fuel assembly transitions from a reactor core shutdown temperature to a reactor core operating temperature, with the second position placing the bimetallic spring in contact with a corresponding grid of an adjacent nuclear fuel assembly located in a reactor core.
2. The nuclear fuel assembly of claim 1 wherein the bimetallic spring has an elongated dimension and the elongated dimension of the bimetallic spring extends transverse to the elongated dimension of the nuclear fuel assembly.
3. The nuclear fuel assembly of claim 2 wherein the bimetallic spring is continuous and extends across several of the grid cells.
4. The nuclear fuel assembly of claim 1 wherein the at least one grid of the plurality of grids is a mid-grid.
5. The nuclear fuel assembly of claim 1 wherein the at least one grid of the plurality of grids is one of an upper grid or a lower grid or both an upper grid and a lower grid.
6. The nuclear fuel assembly of claim 1 wherein the bimetallic spring is configured in a rectangular shape having an elongated dimension.
7. The nuclear fuel assembly of claim 6 wherein the elongated dimension of the bimetallic spring extends substantially parallel to the elongated dimension of the nuclear fuel assembly.
8. The nuclear fuel assembly of claim 1 wherein the bimetallic spring comprises stainless steel and either FeNi36 or 64FeNi.
9. The nuclear fuel assembly of claim 8 wherein the bimetallic spring is formed on each corner of the at least one grid of the plurality of grids.
10. The nuclear fuel assembly of claim 1 wherein the peripheral surface area of the at least one grid of the plurality of grids comprises a base metal, and wherein the bimetallic spring is formed by coating the base metal with a material having a lower coefficient of thermal expansion than the base metal.
11. The nuclear fuel assembly of claim 1 wherein the bimetallic spring is formed on a corner of the at least one grid of the plurality of grids.
12. The nuclear fuel assembly of claim 1 wherein the bimetallic spring does not protrude outwardly from the plane in the first position and protrudes outwardly from the plane in the second position to contact the corresponding grid of the adjacent nuclear fuel assembly.
13. The nuclear fuel assembly of claim 1 wherein the bimetallic spring is configured in a round disc shape.
14. The nuclear fuel assembly of claim 13 wherein the bimetallic spring has a dome when exposed to the reactor core operating temperature.
15. The nuclear fuel assembly of claim 13 further comprising relief holes spaced around the circumference of the bimetallic spring.
16. The nuclear fuel assembly of claim 1 wherein the bimetallic spring comprises a base material coated with a material having a different coefficient of thermal expansion than the base material.
17. The nuclear fuel assembly of claim 1 wherein the bimetallic spring comprises a lamination of a first material and a second material, wherein the first material has a different coefficient of thermal expansion than the second material.
Description
BRIEF DESCRIPTION OF THE DRAWINGS
(1) A further understanding of the invention can be gained from the following description of the preferred embodiments when read in conjunction with the accompanying drawings in which:
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DESCRIPTION OF THE PREFERRED EMBODIMENT
(16) The attached figures in
(17) Another embodiment disclosed herein is a bimetallic protrusion spring attached to a fuel assembly top or bottom nozzle 62 and 58, or Inconel top or bottom grid. This feature would provide alignment benefits for conditions such as damaged upper core plate fuel assembly alignment pins that have been removed. The top nozzle 62 or other host component would support itself upon all adjacent nozzles 62 (or other like-adjacent components) with this feature, ensuring alignment with the intent of reducing or eliminating penalties for removed pins. This second feature may be on all the fuel assemblies or just the ones with damaged alignment. However, preferably it is on the fuel assemblies with damaged pins and the adjacent fuel assemblies have recesses 32 in which the springs can seat. Sample calculations for many of the arrangements are also available showing significant load capability can be attained depending on the feature geometry. Thus, this invention employs bimetallic features to provide either fuel assembly alignment benefits or improved fuel assembly response during seismic/LOCA accident conditions.
(18) More specifically, one such feature is the top nozzle alignment spring shown in
(19) Another concept feature is a typical outer grid strap 24 containing a bimetal material spring feature 26 as shown in
(20) Significant load capability can be designed into the features for Seismic/LOCA load absorption. This feature can also be used in reverse, i.e., wherein the spring retracts at operating temperature and is in an expanded state below operating temperature to facilitate alignment of the fuel assemblies when the upper core plate is being installed.
(21) While specific embodiments of the invention have been described in detail, it will be appreciated by those skilled in the art that various modifications and alternatives to those details could be developed in light of the overall teachings of the disclosure. Accordingly, the particular embodiments disclosed are meant to be illustrative only and not limiting as to the scope of the invention which is to be given the full breadth of the appended claims and any and all equivalents thereof.