Spacer grid using tubular cells
11942230 ยท 2024-03-26
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
International classification
Abstract
A spacer grid specifically designed for accident tolerant fuel utilizing fuel rods with SiC cladding for implementation in pressurized water reactors. The spacer grid design allows for ease of SiC fuel rod insertion during the fuel assembly fabrication process by providing a smooth contact geometry. The co-planar support allows the fuel rods to be rotated axially more freely at the grid location than a conventional six-point contact geometry used in existing fuel assembly designs. The fuel rod support cells are attached at their corners which are shared between adjacent support cells.
Claims
1. A nuclear fuel assembly spacer grid comprising: a plurality of tubular support cells having four walls and four substantially flat corners, wherein one of the flat corners is positioned between two of the walls, wherein at least a first pair of adjacent flat corners of adjacent support cells form a single integral corner between the adjacent support cells, wherein the single integral corner is a unitary one-piece corner that is shared between the first pair of the adjacent corners of the adjacent support cells, and wherein the unitary one-piece corner is a part of each of the adjacent support cells; a spring supported from each of the four walls of each of the support cells that extends at least partially into the support cell, with the spring having a contact surface that contacts a fuel rod when the fuel rod is loaded in the support cell; and a hard material coating on the contact surface that is as hard as or harder than SiC.
2. The nuclear fuel assembly spacer grid of claim 1, wherein each unitary one-piece corner is not thicker than 0.018 inch.
3. The nuclear fuel assembly spacer grid of claim 1, wherein the hard material coating is deposited by physical vapor deposition.
4. A nuclear fuel assembly comprising: the nuclear fuel assembly spacer grid of claim 1: a fuel rod comprising a SiC coating and the fuel rod received within one of the support cells.
5. The nuclear fuel assembly spacer grid of claim 1, wherein each of the four walls is bowed inwardly thereby forming a bend.
6. The nuclear fuel assembly spacer grid of claim 5, wherein each bend is centered on an axis running along each respective spring.
7. The nuclear fuel assembly spacer grid of claim 1, wherein each spring is positioned in a center of one of the walls.
8. The nuclear fuel assembly spacer grid of claim 1, wherein the nuclear fuel assembly spacer grid is not welded.
9. The nuclear fuel assembly spacer grid of claim 1, wherein the nuclear fuel assembly spacer grid is produced by additive manufacturing.
10. The nuclear fuel assembly spacer grid of claim 1, wherein each spring is formed from two slits in one of the walls.
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:
(2)
(3)
(4)
(5)
(6)
(7)
(8)
(9)
(10)
DESCRIPTION OF THE PREFERRED EMBODIMENT
(11) Many conventional spacer grids are composed of straight grid straps that are interleaved together to form an egg-crate configuration having a plurality of roughly square cells, many of which support fuel rods. An example of such a conventional fuel grid 10 can be found in
(12) Referring to
(13) As mentioned above, the fuel rods 36 and the array thereof in the assembly 40 are held in spaced relationship with one another by the grids 10 spaced along the fuel assembly length. Each fuel rod 36 includes nuclear fuel pellets 50 and the opposite ends of the rods 36 are enclosed by upper and lower end plugs 52 and 54, to hermetically seal the rod. Commonly, a plenum spring 56 is disposed between the upper end plug 52 and the pellets 50 to maintain the pellets in a tight, stacked relationship within the rod 36. The fuel pellets 50 composed of fissile material are responsible for creating the reactive power of the PWR. A liquid moderator/coolant, such as water or water-containing boron, is pumped upwardly through the fuel assemblies of the core in order to extract heat generated therein for the production of useful work.
(14) To control the fission process, a number of control rods 58 are reciprocally movable in the guide thimbles 44 located at predetermined positions in the fuel assembly 40. Specifically, the top nozzle 48 has associated therewith a rod cluster control mechanism 60, having an internally threaded cylindrical member 62 with a plurality of radially extending flukes or arms 64 such that the control mechanism 60 is operable to move the control rods 58 vertically in the guide thimbles 44 to thereby control the fission process in the fuel assembly 40, all in a well-known manner.
(15) As shown in
(16) As an example, a typical split-mixing vane design 28 can be attached using the proposed geometry in
(17) Accordingly, this invention provides a tubular cell design which allows for a smooth insertion of SiC type fuel rods while also resulting in a low pressure drop as compared to existing grid designs. Such an additively manufactured spacer grid design allows for 1) the implementation of highly detailed yet fully integrated mixing features enhancing thermal and hydraulic performance, 2) minimizing the overall pressure drop (single wall) and 3) increasing overall grid strength for seismic concerns.
(18) 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.