WO1993002456A1 - Element combustible de reacteur nucleaire avec dispositif d'espacement hexagonal en treillis - Google Patents
Element combustible de reacteur nucleaire avec dispositif d'espacement hexagonal en treillis Download PDFInfo
- Publication number
- WO1993002456A1 WO1993002456A1 PCT/DE1992/000548 DE9200548W WO9302456A1 WO 1993002456 A1 WO1993002456 A1 WO 1993002456A1 DE 9200548 W DE9200548 W DE 9200548W WO 9302456 A1 WO9302456 A1 WO 9302456A1
- Authority
- WO
- WIPO (PCT)
- Prior art keywords
- mesh
- nuclear reactor
- trapezoids
- fuel element
- sheet metal
- Prior art date
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/34—Spacer grids
- G21C3/348—Spacer grids formed of assembled non-intersecting strips
-
- Y—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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Definitions
- the invention relates to a nuclear reactor fuel element according to the preamble of claim 1.
- this generic term fs is a diagonal that halves the angle between two abutting sides of this outer web hexagon.
- Nuclear reactor fuel element is known from German Offenlegungsschrift 34 01 630.
- the parallel, shorter base sides and the legs of the two isosceles trapezoids are behind
- a pressurized nuclear reactor unlike a breeding reactor, the important thing is that the fast neutrons generated in nuclear fission are quickly decelerated to thermal speed. Unlike a brood reactor, a thermal pressurized-water nuclear reactor therefore requires a relatively large ratio of
- Coolant which is also a moderator, to nuclear fuel (moderation ratio) in the reactor core.
- Nuclear reactor fuel elements for thermal pressurized water nuclear reactors often have grid-shaped spacers with meshes intended for fuel rods, all of which have the same square contour in a reference plane perpendicular to the fuel rods.
- the cross-sectional center points of the fuel rods in the center of the meshes of these spacers 35 are each positioned in the corner points of mutually identical squares which in the reference plane are points of two sets perpendicular to one another, each of which is an equidistant straight line which is parallel to one another.
- the profile of the speed of the moderator and coolant consisting of water in the longitudinal direction of the fuel rods is strongly pronounced, and indeed the speed of the water in the center of a relevant square is greater than between two fuel rods with the Cross-sectional centers in two adjacent corners of this square.
- the invention has for its object to develop the known nuclear reactor fuel element and to facilitate the holding of the fuel rods.
- a nuclear reactor fuel element of the type mentioned at the outset has the features of the characterizing part of patent claim 1.
- the two mesh sides which are located in the legs of one of the isosceles trapezoids, can be drawn close to the fuel rod in the mesh concerned. These mesh sides can even rest directly on the fuel rod.
- the subclaims relate to advantageous designs of this nuclear reactor fuel element.
- FIG. 1 shows a plan view of the contour of a grid-shaped spacer in a reference plane perpendicular to the fuel rods of a nuclear reactor fuel element according to the invention.
- FIG. 2 shows the contour of a single mesh of the spacer in this reference plane.
- FIG. 3 shows a perspective illustration of two abutting sheet metal webs of the spacer with the contour according to FIGS. 1 and 2.
- a nuclear reactor fuel element with a grid-shaped spacer has two holding plates, between which there is at least one spacer.
- a support rod 2 whose longitudinal axis, the two parallel holding plates at an angle of 90 penetrates *, in one of these two supporting plates is attached to each end.
- This holding rod 2 passes through a mesh of the lattice-shaped spacer with the contour according to FIG. 1.
- This spacing element is, for example, positively held on this holding rod 2 between two sleeves which are firmly seated on the holding rod 2 on the outside.
- Fuel rods 3 arranged from one another and containing nuclear fuel are provided. Each of these fuel rods 3 is guided through a mesh of the spacer with the contour according to FIG. 1 and is held in this mesh with the aid of a spring which presses the fuel rod 3 in question radially against two rigid knobs on mesh walls in this mesh.
- the grid-shaped spacer which has the contour shown in FIG. 1 in a reference plane perpendicular to the holding rod 2 and the fuel rods 3, has upright arranged outer webs made of sheet metal. These outer webs form the sides 4 of a regular outer web hexagon in the contour in the reference plane.
- intersection points S of a first set of equidistant straight lines 5 with a second set of " equidistant straight lines 6 in the reference plane are the positions for the cross-sectional center of the holding rod 2 and the fuel rods 3 in the reference plane.
- the straight lines 5 of the first set are closed two parallel sides 4 of the regular outer web hexagon and the straight lines 6 of the second coulter parallel to two other parallel sides 4 of this regular outer web hexagon.
- the straight lines of each of the two coulters which line 4 of the regular outer web hexagon corners directly adjacent to which the straight lines of the respective coulter are parallel also have the same distance from these sides 4.
- the outer webs are not involved in the mesh walls of the inner meshes of the lattice-shaped spacer, but the mesh walls of these inner meshes are exclusively on two upright sheet metal webs 7 and 7 that are fastened with each web end to the inside of an outer web 8 molded. These sheet metal webs 7 and 8 abut each other flat along a straight line 9. This straight line 9 is at right angles to a diagonal 10 of this regular outer web hexagon bisecting the angle between two abutting sides 4 of the regular outer web hexagon.
- the mesh contour of an inner mesh in the reference plane according to FIG. 1 is composed of the outer contours of two isosceles trapezoids each having two parallel base sides.
- the longer base sides of the two trapezoids both fall over one another with their entire length overlapping the other in straight line 9.
- the two shorter base sides 20 and 21 of the two trapezoids are parallel to one another.
- both shorter base sides 20 and 21 have a different length than the four legs 22 and 23 of the two trapezoids, which are all four of the same length.
- the shorter base sides 20 and 21 both have the same distance from the straight line 9.
- the shorter base 20 of one trapezoid has a greater length than the four legs 22 and 23 of equal length and the shorter base 21 of the other trapezoid has a shorter length than these four legs 22 and 23.
- the Center M of the two longer base sides of the two trapezoids together. At the same time, this center M also falls into an intersection S of the two groups of straight lines 5 and 6 in FIG. 1, which is located within the mesh contour.
- a cylindrical fuel rod 3 arranged within the mesh with the mesh contour according to FIG. 2 lies with its outer surface against two rigid system studs 25 and 26.
- Each of these system studs 25 and 26 is drawn into the mesh in the radial direction on the mesh sides, which are located in the two legs 23 of the trapezoid, with respect to the fuel rod 3 with a circular cross-section, the cross-section center point of which falls in the center M. , whose shorter base side 21 has a shorter length than the shorter base side 20 of the other trapezoid.
- FIG. 2 the mesh contour of a mesh of the lattice-shaped spacer, which is a regular hexagon, is shown in broken lines, as is present in the known nuclear reactor fuel element. Rigid system nubs are also dashed in the mesh of this lattice-shaped
- Fuel rod 3 in that the trapezoids forming the mesh contour have longer base sides, both of which overlap one another with their entire length in a straight line for all, but which only have one common end point.
- the sheet metal webs 7 and 8 of the lattice-shaped spacer with the contour corresponding to FIG. 1 form an outer mesh of the lattice-shaped spacer at their two ends with an outer web.
- Each of these two outer stitches has a stitch contour in the reference plane which the legs and the shorter base side of an isosceles leg open to the interior of this outer stitch
- the longer base of this trapezoid falls on straight line 9.
- the longer base has a center point N, in which an intersection point S of the two sets of equidistant straight lines 4 and 5 is located within the mesh contour.
- the cross-sectional center of the fuel rod 3 located in the two outer meshes thus falls into the center N.
- the mesh walls of this outer mesh in the legs and in the shorter base of the trapezoid are molded onto the sheet metal web 8.
- a rigid system knob 25 and 26 for the fuel rod 3 guided through this outer mesh is advantageously drawn in as in the mesh with the mesh contour according to FIG. 2.
- a compression spring 27 is arranged opposite these two rigid system nubs.
- the cross-sectional center points of three adjacent fuel rods 3 or of the holding rod 2 and two fuel rods 3 adjacent to it are in the desired manner always in the corners of an equilateral triangle arranged.
- the equilateral triangles, one of which is designated 35 in FIG. 1, are congruent.
- the two sheet metal webs 7 and 8 abut each other on two flat sections a and b, and the flat section b of the sheet web 8 has a window c into which the flat section a of
- Sheet metal web 7 is fitted. At its edges, this flat portion a is welded to the edges of the window c in the flat portion b, so that the two flat sides of the portions a of a sheet metal web and b of the other sheet metal web are each in the same plane. In this way, double walls are avoided at the locations of the two sheet metal webs 7 and 8 where these two sheet metal abut each other. A relatively good neutron economy is thereby achieved in the pressurized water nuclear reactor in which the nuclear reactor fuel element is used.
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Filtering Materials (AREA)
Abstract
Pour permettre d'obtenir une dissipation de la chaleur favorable dans un réseau de crayons combustibles en triangle tout en ayant un support des crayons combustibles facile à utiliser, un élément combustible de réacteur nucléaire comporte un dispositif d'espacement en treillis avec une maille intérieure dont le contour est constitué par le contour extérieur de deux trapèzes isocèles dont les grandes bases coïncident avec une droite (9), l'une sur toute sa longueur et l'autre par recouvrement; les deux petites bases (20, 21; 30, 31) de ces deux trapèzes ont le même espacement par rapport à la droite (9), et au moins une de ces petites bases a une longueur différente des quatre côtés de même longueur (22, 25) des deux trapèzes.
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE4123726A DE4123726A1 (de) | 1991-07-17 | 1991-07-17 | Kernreaktorbrennelement |
DEP4123726.9 | 1991-07-17 |
Publications (1)
Publication Number | Publication Date |
---|---|
WO1993002456A1 true WO1993002456A1 (fr) | 1993-02-04 |
Family
ID=6436386
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
PCT/DE1992/000548 WO1993002456A1 (fr) | 1991-07-17 | 1992-07-02 | Element combustible de reacteur nucleaire avec dispositif d'espacement hexagonal en treillis |
Country Status (3)
Country | Link |
---|---|
CU (1) | CU22382A3 (fr) |
DE (1) | DE4123726A1 (fr) |
WO (1) | WO1993002456A1 (fr) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5367549A (en) * | 1993-05-06 | 1994-11-22 | Combustion Engineering, Inc. | Hexagonal grid |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE4410396A1 (de) * | 1994-03-25 | 1995-09-28 | Siemens Ag | Abstandhalter mit hexagonalen Maschen |
Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
BE643251A (fr) * | 1964-01-31 | 1964-07-31 | ||
FR1411464A (fr) * | 1964-10-13 | 1965-09-17 | Atomic Energy Authority Uk | Grille d'écartement pour échangeurs de chaleur |
BE725717A (fr) * | 1968-12-19 | 1969-05-29 | ||
DE3401630A1 (de) * | 1984-01-18 | 1985-07-18 | Kraftwerk Union AG, 4330 Mülheim | Abstandshalter fuer die brennstaebe eines kernreaktor-brennelements |
-
1991
- 1991-07-17 DE DE4123726A patent/DE4123726A1/de not_active Withdrawn
-
1992
- 1992-07-02 WO PCT/DE1992/000548 patent/WO1993002456A1/fr unknown
- 1992-07-17 CU CU9284A patent/CU22382A3/es unknown
Patent Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
BE643251A (fr) * | 1964-01-31 | 1964-07-31 | ||
FR1411464A (fr) * | 1964-10-13 | 1965-09-17 | Atomic Energy Authority Uk | Grille d'écartement pour échangeurs de chaleur |
BE725717A (fr) * | 1968-12-19 | 1969-05-29 | ||
DE3401630A1 (de) * | 1984-01-18 | 1985-07-18 | Kraftwerk Union AG, 4330 Mülheim | Abstandshalter fuer die brennstaebe eines kernreaktor-brennelements |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5367549A (en) * | 1993-05-06 | 1994-11-22 | Combustion Engineering, Inc. | Hexagonal grid |
Also Published As
Publication number | Publication date |
---|---|
CU22382A3 (es) | 1996-01-31 |
DE4123726A1 (de) | 1993-01-21 |
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