U.S. patent number RE31,583 [Application Number 06/220,591] was granted by the patent office on 1984-05-08 for fuel assembly hold-down device.
This patent grant is currently assigned to Combustion Engineering, Inc.. Invention is credited to John J. Hutchinson, Ralph H. Klumb.
United States Patent |
RE31,583 |
Klumb , et al. |
May 8, 1984 |
Fuel assembly hold-down device
Abstract
The invention provides a hold-down device which maintains a net
downward force on a fuel assembly in a nuclear reactor under all
thermal and hydraulic conditions in the reactor core region. The
hold-down device is particularly applicable in reactors having
stainless steel support barrels and Zircaloy guide tubes. The
hold-down device of the preferred embodiment of the invention is
comprised of coil springs coaxially disposed about alignment posts
which extend upwardly from the top end plate of each fuel assembly.
A hold-down plate is slideably mounted on the alignment posts and
the coil springs are interposed, in compression, between the
hold-down plate and the top end plate. In use, the coil springs
bias the hold-down plate upwardly against a core alignment plate to
provide a downward force on the fuel assembly. The hold-down plate
may also serve as a lifting surface for the fuel assembly during
fuel handling.
Inventors: |
Klumb; Ralph H. (Simsbury,
CT), Hutchinson; John J. (Windsor, CT) |
Assignee: |
Combustion Engineering, Inc.
(Windsor, CT)
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Family
ID: |
26842904 |
Appl.
No.: |
06/220,591 |
Filed: |
December 29, 1980 |
Related U.S. Patent Documents
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Application
Number |
Filing Date |
Patent Number |
Issue Date |
|
Reissue of: |
145374 |
May 20, 1971 |
03770583 |
Nov 6, 1973 |
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Current U.S.
Class: |
376/364;
976/DIG.59; 976/DIG.102; 376/449; 976/DIG.65 |
Current CPC
Class: |
G21C
3/331 (20130101); G21C 3/32 (20130101); G21C
5/06 (20130101); Y02E 30/40 (20130101); Y02E
30/30 (20130101) |
Current International
Class: |
G21C
5/06 (20060101); G21C 3/32 (20060101); G21C
5/00 (20060101); G21C 3/33 (20060101); G21C
019/02 () |
Field of
Search: |
;376/364,449,445,444,438,440 |
References Cited
[Referenced By]
U.S. Patent Documents
Foreign Patent Documents
Other References
RESAR-3S, pp. 4.2-9-4.2-13 (7/75) Maine Yankee, Exhibit 1. .
Design and Performance of C.E. All-Zircaloy Fuel Assemblies,
Anderson et al, TIS-6138, pp. 1-9, 5/79..
|
Primary Examiner: Cangialosi; Sal
Attorney, Agent or Firm: Ristas; L. James
Claims
What we claim is:
1. In a nuclear fuel assembly including, .Iadd.a plurality of
.Iaddend.longitudinally extending rigid support .[.means.].
.Iadd.tubes.Iaddend.; upper and lower end fittings supported by
said support .[.means.]. .Iadd.tubes .Iaddend.at opposite ends
thereof; a plurality of elongated fuel elements in parallel
relationship and extending substantially between said upper and
lower end fittings and supported by said support .[.means.].
.Iadd.tubes.Iaddend., hold-down apparatus for said fuel assembly in
which said upper end fitting comprises:
an end plate supported by said support .[.means.]. .Iadd.tubes
.Iaddend.against downward motion relative thereto and extending
transversely thereof;
.[.alignment means.]. .Iadd.a plurality of hollow cylindrical posts
.Iaddend.projecting longitudinally upward from and supported
against upward motion relative to said end plate, .Iadd.each of
.Iaddend.said .[.alignment means.]. .Iadd.posts .Iaddend.having an
outwardly enlarged shoulder affixed thereto and spaced upwardly
from said end plate.[.;.]..Iadd., said posts and end plate
including passageways extending vertically therethrough in registry
with said tubes whereby a control element may be inserted
therewithin into said fuel assembly; .Iaddend.
force transmitting means slidably mounted on said .[.alignment
means.]. .Iadd.posts .Iaddend.and movable therealong between said
shoulder and said end plate.Iadd., and including a hold-down plate
having at least one hub portion, an aperature in and extending
through said hub portion for relative slidable passage therethrough
of said posts, .Iaddend.and .[.having a portion thereof.]..Iadd.leg
portions .Iaddend.extending laterally beyond said .[.shoulder.].
.Iadd.shoulders .Iaddend.for receiving a downward force applied to
said .Iadd.leg .Iaddend..[.portion.]. .Iadd.portions.Iaddend.;
and
spring means .Iadd.coaxially disposed about a plurality of said
posts and being .Iaddend.interposed .Iadd.in compression
.Iaddend.between said force transmitting means and said end plate
for biasing said force transmitting means upwardly from said plate
whereby a said downward force on said force transmitting means is
yieldably transmitted to said fuel assembly. .[.2. The apparatus of
claim 1 wherein said force transmitting means comprise a hold-down
plate having at least one hub portion; an aperture in and extending
through said hub portion for relative slidable passage therethrough
of said alignment means; and leg means extending substantially
radially outward from said hub portion beyond said enlarged
shoulder on said alignment means..]. 3. The apparatus of claim
.[.2.]. .Iadd.1 .Iaddend.wherein said .[.alignment means comprise a
plurality of cylindrical posts extending upwardly from said end
plate and.]. .Iadd.posts are .Iaddend.symmetrically disposed about
the vertical axis passing through the center of gravity of said
fuel assembly; and said hold-down plate includes said same plural
number of apertured hub portions for relative insertion
therethrough of said .[.alignment.]. posts, said hub portions being
joined and positioned relative to one another .[.and.]. by said leg
.[.means.]. .Iadd.portions.Iaddend.. .[.4. The apparatus of claim 1
wherein said spring means comprise a coil spring, said coil spring
being in compression and coaxially disposed about said alignment
means..].
. The apparatus of claim 3 wherein said spring means comprise coil
springs, said coil springs being in compression and coaxially
disposed about a plurality of said .[.alignment.]. posts. .[.6. The
apparatus of claim 1 wherein said fuel assembly includes a hollow
tube open at its upper end and extending at least the full extent
of said fuel elements parallel thereto and in vertical alignment
with said alignment means; and said alignment means and said end
plate include a passageway extending vertically therethrough in
registry with said hollow tube whereby a control element may be
inserted therewithin into said fuel assembly..]. .[.7. The
apparatus of claim 3 wherein said fuel assembly includes hollow
tubes open at their upper ends and extending at least the full
extent of said fuel elements thereto and in vertical alignment with
alignment posts; and said alignment posts and said end plate
include passageways extending vertically thereto in registry with
said hollow tubes whereby a control element may be inserted
therewithin into said fuel assembly..]. .[.8. The apparatus of
claim 7 wherein said hollow tubes comprise said support means
extending between said fuel assembly end fittings..]..Iadd. 9. The
apparatus of claim 5 wherein the posts are rigidly secured to the
end plate. .Iaddend.
Description
BACKGROUND OF THE INVENTION
The present invention relates to nuclear fuel assemblies and more
particularly to hold-down devices for nuclear fuel assemblies. More
particularly still the invention, in its preferred embodiment,
provides an improved fuel assembly hold-down device having
additional utility as the lifting surface during handling of the
fuel assembly.
In most nuclear reactors the core portion is comprised of a large
number of elongated fuel elements grouped in and supported by
frameworks referred to as fuel assemblies. The fuel assemblies are
generally elongated and receive support and alignment from upper
and lower alignment and support grids. These grids, often referred
to as support or alignment plates, are themselves directly or
indirectly attached to a support barrel which surrounds the entire
core and extends beyond the ends thereof. In the most common
configuration the axis of the core support barrel extends
vertically and the various fuel assemblies are also arranged
vertically and receive support by resting at their lower ends upon
the lower support plate.
Local temperatures at various locations within the core may vary
greatly and accordingly the expansion experienced by the various
materials and elements in the core region may vary from location to
location. Further because the materials used in the core region are
not all the same, they exhibit different thermal growth
characteristics. The thermal expansion of the various members in
the core region in the axial or vertical direction may be quite
significant, particularly at the temperatures found within a
nuclear reactor and because the length of some of the members
involved may be 12-15feet or more. For these reasons, the fuel
assemblies are not usually attached to the upper and lower
alignment plates but rather are supported in a manner which permits
some relative motion therebetween. This axial thermal expansion
differential between the fuel assemblies and the core support
barrel is generally accommodated by insuring that the axial spacing
between the upper and lower core support and alignment plates is
somewhat greater than the axial length of the fuel assemblies for
the entire range of thermal conditions in the core region.
In order to facilitate handling and installation of the fuel
assemblies, they are generally not secured to the lower core
support plate and rely upon axially movable alignment posts
extending downwardly through guide holes in the support plate for
lateral alignment. In most reactors a fluid coolant, such as water,
is directed upwardly through apertures in the lower core support
plate and along the fuel rods in the various fuel assemblies to
receive the thermal energy therefrom. The physical configuration of
the various fuel assemblies is such that the coolant may experience
a significant pressure drop in passing upwardly through the core
region. This pressure drop necessarily produces a lifting force on
the fuel assemblies. In some instances, the weight of the fuel
assembly is sufficient to overcome the upward hydraulic lifting
forces under all operating conditions. However, this is often not
the case, particularly when the coolant density is high as at
reactor startup and additionally because of increasing coolant flow
rates. When the hydraulic forces in the upward direction on a
particular fuel assembly are greater than the weight of that fuel
assembly, the net resultant forces on the fuel assembly will be in
the upward direction and will cause the assembly to move upward
into contact with the upper core alignment plate. This motion of a
fuel assembly, if uncontrolled, may result in damage to the fuel
assembly and its fuel rods or to the upper alignment plate and
must, therefore, be avoided. In order to prevent hydraulic lifting
of the fuel assemblies various hold-down devices have been
employed.
For the most part the vertically extending structural members of a
fuel assembly and the core support barrel have been of the same
material, stainless steel. Because they have been of the same
material, the axial thermal expansion differential between them has
been greatly limited and only small variations in the spacing
between the upper end of the fuel assembly and the upper core
alignment plate have existed. Leaf springs acting between the upper
core alignment plate and the upper end of a fuel assembly have
generally been sufficient to overcome any lifting of the fuel
assemblies.
More recently, however, the vertically extending structural members
of a fuel assembly have been fabricated of Zircaloy. This is
particularly the case when the vertically extending structural
members of a fuel assembly are the guide tubes into which control
rod fingers are inserted. Because the materials used in the
vertically extending support structure of the fuel assemblies are
different than that used in the core support barrel, the
opportunity for a significant thermal expansion differential is
created. Increasing temperatures in the core region and increasing
length of fuel assemblies serve to further aggrevate the thermal
expansion differential problem. As an example, in present reactors
having a stainless steel core support barrel and fuel assemblies
supported by Zircaloy guide tubes, the gap between the fuel
assembly and the upper core alignment plate may vary 5/8 of an inch
or more due to the linear expansion differential. The hold-down
means employed must be capable of providing an adequate hold-down
force to the fuel assembly over the entire possible gap range. The
leaf spring, however, is inherently a low deflection device and for
the spring size limitations dictated by the reactor core
environment, is generally incapable of providing the necessary
hold-down forces over the entire range of gap distances which might
be encountered.
SUMMARY OF THE INVENTION
There is provided in the present invention a hold-down device which
is capable of providing adequate hold-down forces to a nuclear fuel
assembly over the full range of thermal expansion differential
distances which might be encountered in a reactor. The hold-down
device is readily adaptable to existing pressurized water reactor
fuel assembly configuration, as well as others. The fuel assembly
hold-down device may be preloaded to accommodate the differential
thermal expansion between the fuel assembly and the core barrel as
well as mechanical tolerance accumulations without reducing the
hold-down force below a preset value. The hold-down device, in its
preferred embodiment, additionally serves as the lifting surface
for each fuel assembly during refueling and handling of the
assembly.
According to the present invention, a fuel assembly hold-down
device is comprised of a hold-down plate and coil spring means in
compression serially interposed between the upper core alignment
plate and the upper end fitting of the fuel assembly. The coil
spring in compression acts to bias the fuel assembly downwardly
against hydraulic forces in the upward direction and is resiliently
deflectable or compressable over the entire range of thermal
expansion differential distances which might be encountered in a
reactor. More particularly, the hold-down device of the invention
provides one or more alignment posts which may be extensions of the
control element guide tubes extending upwardly from the upper end
fitting of a fuel assembly and about which the coil springs are
coaxially disposed. Such an arrangement laterally restrains the
coil springs during operation of the hold-down device and serves to
capture the spring in the unlikely event of fracture. The hold-down
plate is formed with apertures therein. The aperatures are of a
size and location which permit slideable movement therethrough of
at least a portion of each of the alignment posts. In the preferred
embodiment of the invention, the alignment posts have radially
enlarged shoulders at their upper ends which limit the upward
travel of the hold-down plate relative to the fuel assembly. The
hold-down plate serves as a force bearing and pressure transmitting
member which is interposed between the upper core alignment plate
and the coil spring. Apertures existing in the upper core alignment
plate are vertically in registry with the alignment posts on the
fuel assembly and are sized to permit slideable insertion thereinto
of the enlarged shoulder portions of the alignment posts. The
alignment posts may move upwardly and downwardly within the
apertures in the upper core alignment plate to accommodate the
spacing change between the upper core alignment plate and the fuel
assembly which occurs due to the thermal expansion
differential.
In the preferred embodiment of the invention, the hold-down plate
is formed with horizontally extending leg portions which preferably
are positioned symmetrically about the axial center of gravity of
the fuel assembly such that they serve as a lifting surface for a
fuel assembly grabbing tool when the fuel assembly is being
handled. This additional capability of the hold-down device of the
invention is afforded because upward movement of the hold-down
plate is restricted by the shoulders on the alignment posts and the
alignment posts in turn are rigidly secured to the structural
framework of the fuel assembly.
BRIEF DESCRIPTION OF THE DRAWINGS
FIG. 1 is a vertical section view of a nuclear reactor in
accordance with the concepts of the invention.
FIG. 2 is a fragmentary side view of a fuel assembly extending
between upper and lower core alignment plates at a control element
assembly location and having a section showing the hold-down device
of the invention.
FIG. 3 is a top end view of a fuel assembly end fitting
incorporating the hold-down device of the invention.
FIG. 4 is an enlarged sectional view illustrating the juncture of a
guide tube with the fuel assembly upper end fitting.
FIGS. 5a and 5b are partial side views of a fuel assembly at a core
location not having a control element assembly and showing the
hold-down device under conditions of minimum and maximum spacing
respectively between the fuel assembly and the upper alignment
plate.
FIG. 6 is a side view of the upper portion of a fuel assembly
incorporating the hold-down device of the invention and showing the
coupling member of a fuel handling machine poised thereabove.
DESCRIPTION OF THE PREFERRED EMBODIMENT
Referring first to FIG. 1 there is illustrated the reactor pressure
vessel 10 for a pressurized water reactor. Pressure vessel 10
extends generally in a vertical direction and has coolant inlet
means such as nozzle 12 and coolant exit means such as nozzle 14
which provide entry and egress for coolant, in this instance water,
passing through the reactor. A stainless steel core support barrel
16 is rigidly attached to and supported by pressure vessel 10. Core
support barrel 16 contains the reactor core 18 supported upon core
support assembly 20. Core support assembly 20 is rigidly affixed to
core support barrel 16 at or near the lower end thereof and
includes at its upper extent core support plate 22. An upper guide
structure 24 is also contained in the core support barrel 16 and is
rigidly affixed to the barrel above core 18, usually at the upper
end of core support barrel 16. Upper guide structure 24 principally
houses shrouds 26 for control element assemblies 28 and includes at
its lower extent the upper core alignment plate 30. The shrouds 26
are joined to alignment plate 30 to form an integral structure with
guide structure 24. Reactor core 18 is comprised of a plurality of
vertically extending nuclear fuel assemblies 32 arranged in a
substantially circular geometry. A typical reactor contains more
than 200 of such fuel assemblies 32. The coolant flow path within
pressure vessel 10 as indicated by arrows 34 is from inlet nozzle
12 downwardly between pressure vessel 10 and core support barrel 16
into the area of core support assembly 20 and upwardly through
various coolant openings in core support plate 22 through the fuel
assemblies 32 in core 18, and ultimately out through outlet nozzle
14.
A typical fuel assembly 32, seen more clearly in FIG. 2, is
comprised of five vertically extending parallel Zircaloy guide
tubes 36 coextensive with one another and rigidly attached to upper
and lower end fittings 38 and 40, respectively. Guide tubes 36
provide the vertical structural framework for fuel assembly 32. A
plurality of rectangular Zircaloy spacer grids 42 are positioned at
various elevations along guide tubes 36 and are welded thereto.
Fuel rods 44 extend in parallel vertical arrangement within fuel
assembly 32 and their pitch over the full length of the fuel
assembly is maintained by spacer grids 42. A large number of fuel
rods 44, for instance 176, are individually retained by
compartments in the several spacer grids 42. A retention grid 46
welded to the upper portion of the lower and fitting 40 consists of
spring strips interlocked in egg crate fashion and welded to
perimeter strips. Overlapping spring fingers, formed within the
spring strip, engage a machined groove in the lower end of each
fuel rod 44. In this manner all rods 44 are both axially and
laterally restrained.
Lower end fitting 40 is comprised essentially of a lower end plate
48 having alignment posts 50 mechanically secured thereto and
depending downwardly therefrom. Alignment posts 50 fit slideably
into holes in the core support plate 22 and provide the necessary
vertical support and lateral alignment of the lower end of the fuel
assembly 32. In some core designs, the core support plate has the
alignment posts affixed thereto and the posts are slideably engaged
by holes in the fuel assembly lower end fitting. The length of
alignment posts 50 is sufficient to ensure, that even in the event
of maximum possible upward lifting of fuel assembly 32 during an
accident, some part of alignment post 50 will be retained by core
support plate 22 and prevent lateral movement of the fuel assembly.
In order to facilitate installation and removal of each fuel
assembly, the alignment posts 50 are not captured in a way which
restricts their vertical movement.
The upper end of each fuel assembly 32 includes an upper end
fitting 38 which is mechanically secured to guide tubes 36 in a
manner to be discussed more thoroughly below. Included within upper
end fitting 38 are an upper end plate 52 extending transversely of
the vertically extending guide tubes 36 and alignment means, such
as upwardly extending alignment posts 54. As earlier mentioned an
upper core alignment plate 30 affixed to core support barrel 16
extends horizontally of the core support barrel and is located
slightly above the end plates 52 of the fuel assemblies 32 making
up core 18. Holes in alignment plate 30 are positioned and sized to
provide close slideable engagement of the alignment posts 54. In
this manner alignment plate 30 provides the alignment of the upper
ends of the fuel assemblies 32.
In the preferred embodiment of the invention, alignment posts 54
are axially co-incident with guide tubes 36 and have passageways
extending axially therethrough which are co-incident with the
interior passages of the guide tubes. The control element
assemblies 28 of the present embodiment each comprise five parallel
elongated downwardly extending control fingers which are insertable
into and withdrawable from the fuel assemblies 32 by way of guide
tubes 36. As seen in FIG. 2, the alignment plate 30 has a single
large hole extending therethrough at each control element assembly
location. The hole is sized and shaped to allow total insertion of
a control element assembly 28 into a fuel assembly 32 while
laterally restraining the outer most of alignment posts 54. Because
not all fuel assemblies 32 have control element assemblies 28, the
alignment holes in plate 30 at those locations need not extend
entirely through alignment plate 30 and each alignment post 54 may
be received in an individual hole, as seen in FIGS. 5a and 5b.
The distance between lower core support plate 22 and upper core
alignment plate 30 is such that a gap or spacing "d" will exist
between upper core alignment plate 30 and upper end plate 52. Gap
"d" exists to accommodate mechanical tolerances and the thermal
expansion differential exhibited between fuel assembly 32 and core
support barrel 16 in the vertical direction. In the present
instance wherein guide tubes 36 are more than 13 feet in length and
are of Zircaloy with core support barrel 16 being of stainless
steel, the gap d between end plate 52 and alignment plate 30 can
vary 5/8 of an inch or more between the cold ane hot extremes of
reactor operation. The slideable engagement of alignment posts 50
by the holes in core support plate 22 permit some upward movement
of an entire individual fuel assembly 32 in the event that the
hydraulic lifting forces of the coolant moving upwardly through
core 18 are greater on the fuel assembly 32 than the weight of the
fuel assembly.
Even though a fuel assembly 32 might weigh as much as 1400 lbs.,
the upward hydraulic forces directed thereagainst in present
reactors, particularly when the coolant is cold and has greatest
density, is often sufficient to lift the fuel assembly upward from
core support plate 22 and into contact with upper alignment plate
30. In order to prevent such lifting, the fuel assembly hold-down
device of the invention is employed. According to the invention,
the fuel assembly hold-down device includes coil spring means, such
as coil springs 56, in compression and acting between alignment
plate 30 and fuel assembly upper end plate 52 to provide a downward
force against fuel assembly 32. The coil spring means, unlike an
inherently low deflection device such as a leaf spring, is capable
of a much greater range of deflection than a leaf spring of
comparable size. Because size, economy and simplicity are important
in providing an effective hold down for the fuel assemblies the
coil spring means are preferred in providing the hold-down
function.
According to the preferred embodiment and as seen in FIG. 3, five
alignment posts 54 axially co-incident with the five guide tubes 36
are arranged such that one alignment post and guide tube extend
axially through the center of fuel assembly 32 and the other four
are spaced radially outward therefrom and extend parallel thereto.
Alignment posts 54, upper end plate 52 and guide tubes 36 are
mechanically joined to form an integral structure. Upper end plate
52, seen most clearly in FIG. 3, is a cast metal structure having
coolant openings 58 therein through which coolant exhausts from the
fuel assembly. Additionally, five holes extend through the plate at
the locations where the guide tubes 36 and the alignment posts 54
are joined to plate 52.
As seen in FIG. 4, the lower ends of stainless steel guide posts 54
are pressed into the proper holes in end plate 52. The inner wall
of alignment post 54 is recessed and threaded near its lower end
and forms shoulder 59. The upper end of guide tube 36 is enlarged
radially outwardly forming shoulder 61 for axial mating engagement
with shoulder 59 in alignment post 54. A nut 62 disposed about
guide tube 36 is inserted upwardly between guide tube 36 and
alignment post 54 and is threaded into engagement with the threads
in post 54 to maintain the axial engagement therebetween. Locking
means 64 are affixed, as by welding to end plate 52 and engage nut
62 in a manner preventing unthreading rotation of the nut. This
arrangement provides a unitary structure between alignment posts
54, end plate 52 and guide tubes 36. The central alignment post 54,
because of the difficulty of access thereto may be threaded into
plate 52 and guide tube 36 slideably engaged therewithin.
Each of the alignment posts 54 is generally cylindrical in shape
and extends several inches above upper end plate 52. The upper end
portion of each alignment post 54, generally about 1 inch, is
radially enlarged to form shoulder 66, the function of which is
discussed below. The alignment hole or holes in alignment plate 30
are sized to accommodate close sliding engagement of the radially
enlarged portion of each alignment post 54. The coil springs 56
used to provide the hold-down forces on the fuel assembly are
coaxially disposed about one or more of the alignment posts 54.
While it might be possible in some arrangements to use only one
coil spring 56 about the central alignment post 54, a more
desirable arrangement is obtained wherein coil springs 56 are
coaxially disposed about each of the four outer alignment posts 54
and act against hold-down plate 68. This arrangement is only one of
several possible but provides a symmetrical placement of the
springs and allows each spring to be sized to provide only
one-fourth of the overall downward force needed.
Moveable hold-down plate 68 is slideably mounted on alignment posts
54 and is capable of movement between end plate 52 and the shoulder
66 on the alignment posts. Shoulders 66 restrict the upward travel
of hold-down plate 68 relative to fuel assembly 32, making the
plate an integral part thereof. The hold-down plate 68 of the
invention includes hub portions 70 with apertures 72 extending
vertically therethrough and sized to permit slideable passage
therethrough of said alignment posts 54. The several hub portions
70 have legs 74 extending radially outward from them in a
horizontal direction, and in the preferred embodiment legs 74 serve
to interconnect hub portions 70 making up hold-down plate 68. The
radially outer most portions of a hold-down plate 68 extend
sufficiently beyond the alignment hole or holes in plate 30 to
engage the lower surface of plate 30. Because hold-down plate 68
additionally serves as a lifting surface in handling fuel assembly
32 as will be discussed more thoroughly below, these lifting
surfaces are preferably symmetrically disposed about the vertical
center line of gravity of fuel assembly 32.
The coil springs 56 which serve to provide the required hold-down
forces are coaxially disposed about various ones of the alignment
posts 54 between upper end plate 52 and the hold-down plate 68.
Springs 56 are sized and preloaded to ensure that a net downward
force of 150 lbs. will be maintained on fuel assembly 32 for all
normal and anticipated transient flow and temperature conditions.
The cyclic loads on the spring are minimal since the spring
operates over an extended range, as seen in FIGS. 5a and 5b, only
during reactor startup and shutdown conditions. In the example of
the preferred embodiment, each spring 56 is fabricated of Inconel
X750, has a free length of about 4.5 inch, an internal diameter of
1.5 inch, an external diameter of 1.8 inch, a wire size of 0.135
inch, and has 81/2 coils yielding a spring rate of 17 lbs. per
inch. As disposed about alignment posts 54, each spring 56 is held
captive in the event of a spring fracture at almost any point in
the spring.
As seen more clearly in FIGS. 5a and 5b, the hold-down plate 68
which is upwardly biased by coil springs 56 acts against the under
side of upper core alignment plate 30 resulting in a downward force
against upper end plate 52 and accordingly fuel assembly 32. During
the fuel loading operation the various fuel assemblies 32 are
loaded into the reactor and the upper guide structure 24 which
includes upper alignment plate 30 rigidly affixed thereto, is then
lowered into place and rigidly joined to core support barrel 16 at
or near the top thereof. The vertical positioning of alignment
plate 30 provides a gap at cold conditions between alignment plate
30 and upper end plate 52 having a distance, d.sub.1, The gap
distance is smallest at reactor cold conditions and d.sub.1 will
normally be about 2.4 inches. As seen in FIG. 5a, this gap distance
is such that hold-down plate 68 is moved downwardly along alignment
post 54 against the upward force of springs 56 resulting in a
significant downward force against fuel assembly 32. This is the
preload mentioned earlier. As the temperature in the core 18
increases during reactor operation, the differences between the
linear thermal expansions of fuel assembly 32 and core support
barrel 16 result in an increased gap distance, d.sub.2, and
accordingly the spring biased hold-down plate 68 which acts
upwardly against alignment plate 30 is permitted to slide upwardly
along alignment posts 54 to the extent necessary. This somewhat
reduces the downward force which the springs exert against fuel
assembly 32, however, as previously mentioned the initial preload
on springs 56 at the time of installing guide structure 24 is such
that, even when maximum gap distance d.sub.2 occurs, there results
a net downward force on the fuel assembly of about 150 lbs.
The axial length of alignment post 54 above upper end plate 52 is
sufficient to ensure that the alignment post will always be
laterally engaged by alignment plate 30. Further still, the
radially enlarged shoulder 66 of each of the several alignment
posts 54 is sufficiently distant from upper end plate 52 that even
for a maximum gap distance, d.sub.2, which occurs when the reactor
is hot, the upper core alignment plate 30 will continue to exert a
downward force against hold-down force against hold-down plate 68
and accordingly on fuel assembly 32.
The shoulders 66 on alignment posts 54 restrict the upward travel
of hold-down plate 68, as mentioned above, with the result that
hold-down plate 68 forms a lifting surface for fuel handling means
during fueling operations. A typical fuel assembly coupling member
76, as seen in FIG. 6, is employed to lift and move individual fuel
assemblies 32 during fueling and refueling operations. Fuel
coupling member 76 is usually positioned at the lower end of a
rotatable and translatable shaft. Those fuel assemblies 32 which
receive control element assemblies will normally be moved with the
control elements fully inserted thereinto. This will dictate the
number and geometry of slots 78 in coupling member 76. Typically,
the upper or head portion of a control element assembly 28 appears
to coupling member 76 as a vertical extension of hold-down plate
68. Accordingly, slots 78 are spaced at 90.degree. intervals about
the cylindrical coupling member 76 and are axially long enough to
receive hold-down plate 68 and a control element head portion, if
present. The coupling member 76 is positioned above a fuel assembly
32 with slots 78 aligned with the legs 74 on hold-down plate 68.
Coupling member 76 is then moved downwardly over legs 74 and
rotated and raised slightly to supportingly engage legs 74 in seats
80. In this manner the fuel hold-down device of the invention
serves also as the lifting surface for the fuel assembly during
handling thereof.
It should be appreciated that, while the fuel assembly hold-down
device of the preferred embodiment is affixed to each fuel assembly
and may also be used as a handling surface, the scope of the
invention would also include a similar hold-down device employing
coil springs wherein the alignment posts extend downwardly from the
upper core alignment plate and into holes in the fuel assembly
upper end fitting.
While we have illustrated and described a preferred embodiment of
the invention, it is to be understood that such a merely
illustrative and not restrictive and that variations and
modifications may be made therein without departing from the spirit
and scope of the invention. We, therefore, do not wish to be
limited to the precise details set forth but desire to avail
ourselves of such changes as fall within the purview of the
invention.
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