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| United States Patent | 4013121 |
| Link to this page | http://www.wikipatents.com/4013121.html |
| Inventor(s) | Berger; Wolfgang (Erlangen, DT);
Rottger; Hans (Weiher, DT) |
| Abstract | A steam generator has an upstanding tube bundle radially enclosed by a
vertical cylindrical wall, the tube bundle being centered within the wall
by a tube spacer grid connected to the inside of the wall by keys and
keyways which can slide vertically relative to each other, relieving the
tube bundle and wall from mechanical stressing due to vertical thermal
expansion and contraction causing relative vertical movement between the
tube bundle and wall. |
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Title Information  |
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Drawing from US Patent 4013121 |
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Steam generator, tube-bundle centering arrangement |
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| Publication Date |
March 22, 1977 |
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| Filing Date |
July 15, 1974 |
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| Priority Data |
Jul 25, 1973[DT]2337791 |
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Title Information  |
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Description  |
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BACKGROUND OF THE INVENTION
This invention relates to the type of steam generator having a tube sheet,
a heat-exchanger tube bundle formed by a plurality of interspaced tubes
having ends mounted in the tube sheet and extending therefrom and a
cylindrical wall which surrounds the tube bundle. To hold the tube bundle
centered inside of the cylindrical wall, one or more tube spacer grids are
used each formed by a ring encircling the tube bundle inside of the
cylindrical wall, the ring mounting criss-crossed bars forming openings
through which the tube bundle's individual tubes extend, and the ring
being connected to the inside of the cylindrical wall to in this way hold
the tube bundle centered within the wall.
The above is exemplified by the typical pressurized-water reactor steam
generator. In this case the cylindrical wall is formed by the shroud
within the vertical steam generator housing which has its bottom end
closed by the horizontal tube sheet with the tube bundle being of inverted
U-shape with the bottom ends of its tube legs mounted in the tube sheet.
Inlet and outlet manifolds connect the inlet and outlet legs of the tube
bundle with the main coolant loop of the reactor, and the vertical housing
has a feed-water inlet, its top being provided with a steam dome having a
steam output outlet. The shroud encircles the tube bundle and is spaced
inside of the housing to form therebetween the descent space, the
feed-water rising inside of the shroud and descending via this descent
space to maintain a circulation within the steam generator housing. In
this case the tube bundle should be held centered within the cylindrical
shroud.
The individual tubes are held in their interspaced relationship by a spacer
grid formed by criss-crossed bars forming openings through which the
individual tubes extend, the ends of the bars being mounted by a ring
encircling the tube bundle and which is connected to the inside of the
cylindrical wall surrounding the tube bundle to hold the latter centered
within the cylindrical wall.
When the operating temperature of the steam generator changes, thermal
expansion and contraction causes relative movement between the tube bundle
and wall surrounding this tube bundle. In the case of a pressurized-water
reactor steam generator typically having a vertical tube bundle surrounded
by a vertical shroud with vertical dimensions in the area of 10 m, and
which between cold and hot conditions involve temperature differences of
around 300.degree. C., the tube bundle can receive substantial mechanical
stress when the spacer grid is fixed to the shroud; and since the tube
bundle tubes are of relatively small diameter as compared to their length,
this has been a problem. Any steam generator having a tube bundle
surrounded by a cylindrical wall with the tube bundle centered within the
wall in substantially the same manner, involves the same problem.
SUMMARY OF THE INVENTION
The object of the present invention is to solve the above problem.
According to this invention, the problem is solved by connecting the
spacer grid with the cylindrical wall that surrounds the tube bundle, by
keys and keyways which permit sliding movement longitudinally with respect
to the tube bundle and its surrounding wall, so that the tube bundle and
its surrounding wall are freed from mechanical stress due to the relative
thermal movement that occurs between the tube bundle and the surrounding
wall. At the same time, the connection of the spacer grid ring to the
inside of the cylindrical wall locks the ring against movement
circumferentially with respect to the wall, so by using three or more of
the key and keyway connections between the ring and the wall, the tube
bundle is held accurately centered within the cylindrical wall.
Normally the steam generator uses a plurality of such spacer grids, and in
accordance with the present invention, each of the grids is connected by
the keys and keyways with the wall surrounding the tube bundle. The keys
may be on either the ring or the wall with the keyway formed by the other
of these two parts. Normally the keys and keyways would have rectangular
cross-sections and the bottoms of the keyways can be spaced relative to
the opposing ends of the keys to accommodate radial expansion of the
spacer grid ring, without interfering with the centering function
providing at least three of the connections are used.
In the case of a pressurized-water reactor steam generator, the connections
are made between the rings of the various spacer grids and the inside of
the shroud forming the descent space, the relative motions in this
instance being vertical and radial.
BRIEF DESCRIPTION OF THE DRAWINGS
The presently preferred mode for carrying out the invention is
schematically illustrated by the accompanying drawings in which:
FIG. 1 in vertical section illustrates a pressurized-water reactor steam
generator;
FIG. 2 in cross section shows the key and keyway connections, the keys
being fixed to the spacer grid rings with the keyways formed in the
shroud, in this instance;
FIG. 3 in cross section illustrates an instance when the keys are formed on
the shroud with the keyways formed in the spacer grid rings;
FIG. 4 is a vertical section taken on the line IV--IV in FIG. 2; and
FIG. 5 is a vertical section taken on the line V--V in FIG. 3.
DETAILED DESCRIPTION OF THE INVENTION
The steam generator shown by FIG. 1 has a substantially cylindrical and
vertical housing 1, with the primary header 2 of hemispherical shape
divided by a vertical partition 3 to form the coolant inlet and outlet
manifolds 4 and 5, respectively. The cylindrical shroud 6 extends upwardly
from the horizontal tube sheet 7 which mounts the bottom ends of the inlet
and outlet legs of the inverted U-shaped tube bundle 8, the individual
tubes of which are not shown because of their familiarity to everyone. The
top of the housing 1 is radially enlarged to form the space 9 within which
water separators (not shown) are usually located.
The main coolant loop connections with the manifolds 4 and 5 and the
feed-water inlet are not shown, again because they are familiar. Coolant
from the hot leg of the main loop enters the inlet manifold, goes through
the hot leg of the tube bundle 8, returns to the bundle's cold leg and
goes back to the reactor via the outlet manifold. Feed-water is introduced
to the housing 1 above the tube sheet 7, partially vaporizes the steam
while rising inside of the shroud 6 with the unvaporized feed water
descending via the descent space between the shroud 6 and the housing 1.
Although not shown, the bottom of the shroud 6 provides an opening so that
the descending feed water can flow radially inwardly over the top of the
tube sheet 7 to again rise inside of the shroud 6.
To center the tube bundle 8 within the vertical shroud 6, and to maintain
the interspacing of the individual tubes of the tube bundle, the spacer
grids 10 are used, there being a plurality of these spacer grids
interspaced vertically.
Each spacer grid 10 comprises a ring 11 which encircles the tube bundle and
mounting the ends of the criss-crossed bars 12 and 13 forming the openings
14 through which the individual tubes (not shown) extend. The ends of the
bars may be fastened to the ring 11 in the usual manner.
The vertical cylindrical shroud 6 is centered relative to the vertical
cylindrical housing 1 via a series of struts 17, so if the tube bundle 8
is centered relative to the shroud 6, it is also centered relative to the
housing 1.
The previously referred to key and keyway connections are shown in FIG. 2,
the keys 18 being fixed to the ring 11 and the keyways 19 being formed
inside of the shroud 6. Both the keys and keyways are rectangular in cross
section and provide flat interfacing and vertical sliding surfaces
permitting the relative vertical motion between the tube bundle 8 and
shroud 6. At least three of these vertically slidable connections should
be used, four being shown by FIG. 2. The keys and keyways are interlocked
against movement circumferentially with respect to the ring 11 and the
shroud 6, so the ring 11 is held positively centered relative to the
shroud 6 and, therefore, relative to the cylindrical housing 1.
To accommodate radial thermal expansion and contraction motion, the bottoms
20 of the keyways and the radial ends of the keys 21, by proper
proportioning of the parts, always provide some space even when the
maximum radial expansion motion occurs. In this way there is no
possibility for mechanical stressing in the radial direction of the ring
11 and shroud 6.
In FIG. 2 the keyways are machined into the shroud 6, whereas in FIG. 3 the
keyways 19' are machined into the spacer grid rings 11, the keys 18'
extending radially inwardly from the shroud 17.
The horizontally rectangular contours of the keys and keyways provide for
not only vertical slidability, but also for slidability in the radial
direction of the rings 11.
The described tube bundle centering action is of importance not only in
connection with the operation of the steam generator, but also during its
transport to the reactor site. The keys and keyways may be designed by
appropriate dimension to avoid excessive frictional resistance to the
sliding of the parts relative to each other without interfering with the
centering function.
It is to be understood that in the normal way the spacer grids 10 are held
against vertical displacement relative to the legs of the tube bundle 8,
in the usual way. Although the spacer grids are fixed against motion
relative to the tube bundle legs, all stressing is avoided because each
spacer grid can slide vertically and radially relative to the shroud 6. It
is to be understood that because the tube bundle 8 carries the reactor
coolant, while the shroud 6 is surrounded on both sides by the feed water,
that the tube bundle reaches operating temperatures substantially higher
than the operating temperature of the shroud 6, thus creating the problem
solved by the present invention.
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Description  |
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