Repair fixture

A repair fixture for water-cooled nuclear reactors including an openable reactor pressure vessel having a wall, and conduits passing through the pressure vessel wall for flooding the pressure vessel, includes a sealing box disposed in the opened, flooded pressure vessel, a device connected to the sealing box for pressing the sealing box liquid-tightly against the pressure vessel wall enclosing at least some of the conduits, and a device connected to the sealing box for evacuating the conduits enclosed by the sealing box.

The invention relates to a repair fixture for water-cooled nuclear 
reactors. When making repairs on the walls of a reactor pressure vessel or 
when replacing primary shutdown controls of water-cooled nuclear reactors, 
these primary shutdown controls must be evacuated beforehand. However, 
this is only possible if the water level in the reactor pressure vessel is 
lowered to the extent that it is below the level of the primary shutdown 
controls to be repaired or below the level of the outlets of the 
respective conduits, such as the feedwater distributors. The same applies 
when repairs on the walls of the reactor pressure vessel become necessary. 
In the case of boiling water reactors and pressurized water reactors, this 
presupposes that all of the fuel elements must first have been removed 
from the core barrel. This is extremely costly. Moreover, during 
evacuation of the core barrel and during the lowering of the water level 
in the reactor pressure vessel, a perceptible radiation exposure of the 
operating and maintenance personnel is to be expected. Lastly, the 
lowering of the water level in boiling water reactors requires special 
shielding measures to be taken for the steam separator and steam dryer. 
It is accordingly an object of the invention to provide a repair fixture 
which overcomes the hereinafore-mentioned disadvantages of the 
heretofore-known devices of this general type, and to provide means for 
performing repairs on the primary shutdown controls or even on the walls 
of a reactor pressure vessel, which can be carried out without having to 
lower the water level in the reactor pressure vessel. 
With the foregoing and other objects in view there is provided, in 
accordance with the invention, a repair fixture for water-cooled nuclear 
reactors including an openable reactor pressure vessel having a wall, and 
conduits passing through the pressure vessel wall for flooding the 
pressure vessel, comprising a sealing box disposed in the opened, flooded 
pressure vessel, means connected to the sealing box for pressing the 
sealing box liquid-proof or tightly, abutting against the pressure vessel 
wall enclosing at least some of the conduits, and means connected to the 
sealing box for evacuating the conduits enclosed by the sealing box. 
A sealing box which, according to the invention, can be liquid-tightly 
applied against the pressure vessel wall in the flooded reactor pressure 
vessel in vicinity of the feedwater distributors or conduit connections, 
permits the evacuation of covered wall areas including the feedwater 
distributors and conduit connections present at that location, with the 
reactor pressure vessel flooded. If primary shutdown controls are placed 
at the same level or higher, they are then evacuated at the same time. 
Otherwise, they can be evacuated through the connecting conduits. 
In accordance with another feature of the invention, the conduits are 
feedwater distributors having conduit connections leading to primary 
shutdown controls of the pressure vessel. 
In accordance with a further feature of the invention, there are included 
means disposed in the sealing box for mounting inspection, testing and 
treatment equipment. 
In accordance with an added feature of the invention, there is provided a 
support ring lowerable into the pressure vessel, the sealing box being 
mounted on the support ring. This greatly facilitates handling of the 
rather bulky sealing box. Such a support ring at the same time helps to 
transmit to the wall of the reactor pressure vessel, the compressive 
forces of the sealing box exerted against the inner surface of the wall of 
the reactor pressure vessel. 
In accordance with an additional feature of the invention, there is 
provided a core barrel disposed in the pressure vessel below the conduits, 
the support ring including props engaging the core barrel when the support 
ring is lowered. 
In accordance with again another feature of the invention, the support ring 
has an outer periphery including lateral props engaging the inner surface 
of the pressure vessel wall for absorbing radial compressive forces of the 
sealing box. 
In accordance with again a further feature of the invention, there are 
provided setting cylinders displacing the lateral props against the inner 
surface of the pressure vessel wall. 
The very efficient bracing of the support ring on the core barrel of the 
nuclear reactor defines a reference height of the support ring, from which 
the further displacement of the sealing box relative to the support ring 
can occur. At the same time, a crane will be available for other jobs, 
such as the repositioning of fuel elements, during the running repair 
measures. 
In accordance with again an added feature of the invention, there are 
provided means for displacing the sealing box in radial or circumferential 
direction of the support ring. 
In accordance with again an additional feature of the invention, the 
support ring has an axis of symmetry, and including a guide connected to 
the support ring in which the sealing box is displaceable vertically and 
parallel to the axis of symmetry. In this way, the sealing box can by-pass 
or pass behind guide rods extending along and spaced from the pressure 
vessel wall. 
In accordance with yet another feature of the invention, there are provided 
hydraulic cylinders controlling displacements radially, circumferentially 
and vertically of the sealing box relative to the support ring. 
In accordance with yet a further feature of the invention, there are 
provided guide cams between the sealing box and the support ring adapted 
to a given reactor type for forcibly displacing the sealing box in radial 
direction relative to the support ring. Such cams avoid damage due to 
improper manipulations which are not impossible, to say the least, with 
universal, freely selectable hydraulic adjustment. 
In accordance with yet an added feature of the invention, the pressure 
vessel has an axis of symmetry and contains fuel elements including outer 
fuel elements disposed at a given distance from the axis of symmetry, and 
the conduits are feedwater distributors protruding into the pressure 
vessel, and including a support ring on which the sealing box is mounted, 
the sealing box having a depth in radial direction of the pressure vessel 
being only that which is absolutely necessary to cover the protrusion of 
the feedwater distributors, and the support ring and the sealing box 
leaving an unobstructed inside diameter of the pressure vessel being more 
than twice the given distance, when the sealing box is pressed against the 
pressure vessel wall. 
In accordance with yet an additional feature of the invention, the sealing 
box has rims to be pressed against the pressure vessel wall, and sealing 
lips or gaskets disposed on the rims. 
In accordance with still another feature of the invention, each of the 
gaskets is substantially L-shaped and has a longer and a shorter leg, the 
longer leg being pressed against the pressure vessel wall and having a 
narrow sealing edge and a wide sealing lip, and a shallow fillet between 
the sealing lip and sealing edge. 
In accordance with still a further feature of the invention, the evacuating 
means include a pump. The evacuation of the conduits or feedwater 
distributors covered by the sealing box can be carried out with this 
construction. 
In accordance with still an added feature of the invention, there is 
provided a float switch disposed in the sealing box and connected to the 
pump for controlling the pump. 
In accordance with still an additional feature of the invention, the pump 
is disposed in the sealing box. This simple and expedient solution causes 
the pump to be switched on automatically if necessary in case of leaks or 
other intrusions of water. 
In accordance with another feature of the invention, the pressure vessel 
has a given water level, and including an air venting hose connected to 
the sealing box and leading above the water level. 
In accordance with a further feature of the invention, the conduits are in 
the form of four feedwater distributors connected to the pressure vessel, 
and including grommets and guides being screwed to the support ring and 
movable for repositioning along the periphery of the support ring toward 
the feedwater distributors. The traverses are also needed to manipulate 
other core inserts, such as water separators and are guided in many 
nuclear reactor types for automatic coupling or for exact deposition of 
these core inserts in the pressure vessel area and are not rotatable at 
will about the axis of symmetry thereof. For this reason, this 
construction is especially appropriate for covering the feedwater 
distributors, which are usually offset relative to each other by 
90.degree. or 180.degree.. In this way, the sealing box can be 
repositioned by 90.degree., 180.degree. or 270.degree.. 
In accordance with an added feature of the invention, the support ring is 
divided into sections. This makes the support ring easier to transport to 
the site where it is used and to mount it between the inserts. 
In accordance with an additional feature of the invention, the sealing box 
is at least partly transparent. 
In accordance with again another feature of the invention, there are 
provided transparent windows disposed in the sealing box. 
In accordance with again a further feature of the invention, there are 
provided means disposed in the sealing box for mounting at least one light 
source and a television camera. 
In accordance with again an added feature of the invention, the mounting 
means includes means for moving and adjusting a television camera along 
the sealing box. 
In accordance with a concomitant feature of the invention, the mounting 
means are in the form of remotely controllable carriers for eddy current 
testing probes having ultrasonic testing heads and means for carrying out 
a color penetration method. 
Other features which are considered as characteristic for the invention are 
set forth in the appended claims. 
Although the invention is illustrated and described herein as embodied in a 
repair fixture, it is nevertheless not intended to be limited to the 
details shown, since various modifications and structural changes may be 
made therein without departing from the spirit of the invention and within 
the scope and range of equivalents of the claims.

Referring now to the figures of the drawings in detail and first, 
particularly, to FIG. 1 thereof, there is seen a cross-sectional view of 
the upper part of a biological shield 1 of a containment 2, and an opened 
reactor pressure vessel 3 with a repair fixture 4 according to the 
invention in place. In the representation of FIG. 1, a support ring 5 and 
a sealing box 6 of the repair fixture 4 have been lowered into the flooded 
reactor pressure vessel 3 on a traverse 7 which is suspended from a crane 
harness 8 of the reactor building. The traverse 7 is lowered into the 
reactor pressure vessel 3 far enough for support props 9 to 11 of the 
support ring 5 shown in FIGS. 1 and 2 to sit on an upper rim 12 of a core 
barrel 13. In this position, the sealing box 6 mounted on the traverse 7 
covers a feedwater distributor 14 toward the right side of FIG. 1. The 
sealing box 6 has a rim 15 provided with a peripheral gasket 16 which 
abuts the inner surface of the wall of the reactor pressure vessel 3. 
Three remaining feedwater distributors 17 to 19 shown in FIG. 2 are not 
covered. 
Lateral props 20 to 23, which are adjustable by means of setting cylinders 
24 to 27, brace the support ring 5 against the inner surface of the wall 
of the reactor pressure vessel 3. A pump 28 is attached to the support 
ring 5, below the sealing box 6. The pump 28 has a suction nipple 29 which 
is connected by a hose 30 with the interior of the sealing box. A float 
switch 31 is disposed in the sealing box and is inserted into the 
circulation caused by the pump 28. An outflow nipple 32 of the pump 28 is 
secured through a non-illustrated check valve and discharges directly 
below the pump. 
FIGS. 1 and 3 show that the sealing box 6 is connected with the support 
ring ring 5 through four booms 33 to 36. These booms in turn are 
displaceable parallel to the axis of symmetry 39 of the support ring, i.e. 
vertically in two vertical guides 37, 38 attached to the support ring 5 at 
the top and bottom thereof. FIGS. 1 and 3 also show that the booms 33 to 
36 are not only adjustable in height along the guides 37, 38 on both sides 
of the sealing box 6, but can also be pivoted about these guides. The 
height or vertical adjustment occurs through the use of the hydraulic 
cylinders 40, 41 attached on the support ring, parallel to the guides. In 
order to pivot the booms 33 to 36, two additional hydraulic cylinders 42, 
43 are disposed on the support ring. The hydraulic fluid for the cylinders 
may be pure water to prevent contamination of the flooded pressure vessel. 
As seen in FIG. 3, each of the cylinders 42, 43 have piston rods which 
engage the pivotable end of one of the booms 33, 35. The upper and lower 
ends of the sealing box 6 each carry two guide tracks 44, 45, each of 
which are displaceably guided in the ends of the booms 33 to 36, although 
only two tracks are shown. The sealing box 6 is displaced radially 
relative to the support ring 5, by simultaneously swinging the booms in 
opposite directions. However, since the sealing box 6 is displaceable 
along the guide tracks 44, 45 relative to the booms 33, 35 toward both 
sides, a slide block 46 with a bent guide track 47 can be screwed to the 
support ring 5 above the sealing box. A pin 48 fastened to the sealing box 
engages in the bent guide track 47. The pin 48 which is displaceable along 
the bent guide track 47 of the slide block 46, not only permits the 
sealing box 6 to be advanced radially during the pivoting of the booms 33 
to 36, but simultaneously permits it to be displaced laterally and thus 
guided laterally past the inserts. 
FIG. 4 shows how the gasket or sealing ring 16 is attached to the rim 15 of 
the sealing box 6 by a clamping ring 49. FIG. 4 shows a substantially 
L-shaped contour of the sealing ring 16, which has a fillet 50 in vicinity 
of the abutment surface. The fillet 50 divides the sealing surface of the 
sealing ring into a narrow sealing edge 16' and a greatly extended sealing 
lip 16". The narrow sealing edge will be more easily deformed or pressed 
into unevennesses by the pressing force of the sealing box, while the 
sealing lip is preferably applied through the use of the pressure 
difference. In addition, the sealing lip is pressed against the wall of 
the reactor pressure vessel by a spring blade 63. 
Primary shutdown controls 51', 52' of a water-cooled nuclear reactor, which 
are disposed outside the biological shield 1 and which are connected to 
the reactor pressure vessel 3, may have to be repaired or replaced. 
Heretofore, it was necessary to remove the fuel elements from the core 
barrel to evacuate these primary shutdown controls, so that the reactor 
pressure vessel 3 could be evacuated to the extent that the feedwater 
distributors 14, 17, 18, 19 or the conduit connections would lie above the 
water surface and could be evacuated. According to the invention, after 
removal of the pressure vessel cover and of the other inserts, it is 
sufficient to lower the support ring 5 with the sealing boxes 6 attached 
thereto with the aid of the crane harness 8 of the reactor building, into 
the flooded reactor pressure vessel 3. This is done until the support 
props 9, 10, 11 of the support ring 5 rest on the upper rim 12 of the core 
barrel 13. In this defined position, the lateral props 20, 21, 23 
distributed over the periphery of the support ring can be brought into 
abutment with the inner surface of the wall of the reactor pressure vessel 
3, through the use of the setting cylinders 24 to 27, which are actuated 
by pressurized water. The support ring 5 is then fixed in height as well 
as relative to the axis of symmetry 39 of the reactor pressure vessel 3. 
The booms 33 to 36 carrying the sealing box can therefore be displaced 
along the vertical guides 37, 38 with the vertical hydraulic cylinders 40, 
41, until the sealing box is vertically centered on the feedwater 
distributors 14, 17, 18, 19 to be covered. By then swinging the booms 33 
to 36 apart by means of the hydraulic cylinders 42, 43 disposed below the 
sealing box, the sealing box 6 can be pushed radially outwardly over one 
of the feedwater distributors 14, 17, 18, 19 and against the inner surface 
of the wall of the reactor pressure vessel 3, until its peripheral rim 
having the gasket 16 attached thereto is applied against the inner surface 
of the wall of the reactor pressure vessel. As soon as this is done, the 
pump 28 which is suspended from the support ring below the sealing box 6 
can be turned on and the sealing box can be pumped empty. The water then 
also runs out of the feedwater distributor 14 and the other covered 
conduits including conduit connections 14' and the primary shutdown 
control 51' connected thereto and the water runs into the sealing box 6. 
The water then runs from the sealing box through the outflow nipple 32 of 
the pump 28 into the open, flooded reactor pressure vessel 3, and air 
flows into the sealing box from a venting hose 53. After complete 
evacuation of the sealing box 6 as well as the conduits discharging 
therein, the pump 28 automatically turns off through the float switch 31 
disposed in the sealing box 6. If an intrusion of water or a sufficient 
amount of leakage water has accumulated in the sealing box, the float 
switch 31 switches the pump on again, if necessary. 
In some boiling water reactors, guide rods for other inserts extend upward 
adjacent the feedwater distributors. The guide rods can hinder the radial 
abutment of the sealing box. In such cases, the sealing box 6 can be 
lifted over these obstacles by means of the vertical hydraulic cylinders 
40, 41 before it abuts against the pressure vessel wall. Alternatively, 
the sealing box 6 can be moved past the obstacle laterally, by using the 
slide block 46 adapted to the respective reactor type, if this is easier 
to perform. The sealing box may also be supported by rotating the entire 
support ring 5 by means of the crane harness 8, unless the traverse 7 is 
non-rotationally guided in the reactor pressure vessel. In this way, such 
obstacles can be by-passed with the sealing box or the sealing box can go 
behind the obstacles if the distance from the wall is sufficient. 
The primary shutdown controls 51', 52' evacuated in the above described 
manner can thus be removed without first having to remove the fuel 
elements 13' from the core barrel 13, and the water level in the reactor 
pressure vessel 3 lowered. After completed servicing or replacement of the 
primary shutdown controls and after flooding by actuation of the hydraulic 
cylinders 42, 43, pivoting the booms 33 to 36, the sealing box can be 
pulled off the wall of the reactor pressure vessel again and can be moved 
out of the reactor pressure vessel by the crane harness 8, together with 
the support ring 5. 
If the traverse 7 is not secured against rotation in the reactor pressure 
vessel 3, the other feedwater distributors 17 and 19, which are usually 
offset relative to each other by 90.degree., and the conduit connections, 
can be serviced or replaced in the described manner one after the other. 
This is done by respective rotation of the traverse 7, with the support 
ring 5 attached thereto, about a corresponding angle and by renewed 
lowering. However, if the traverse is secured against rotation, the 
sealing box 6 as well as the grommets, guides and slide blocks on the 
support ring 5 must instead be repositioned, so that the traverse 7 need 
not be rotated about the axis of symmetry 39 of the reactor pressure 
vessel 3 and instead the support ring 5 may be rotated about the axis of 
symmetry and can be suspended from the traverse 7 again. For this reason, 
these structural mambers are secured to the support ring to be unscrewed 
and rescrewed. Transportation to and from the site as well as storage of 
the support ring are also considerably simplified in the case of a 
divided, bolted support ring. 
Due to the fact that the inside diameter of the support ring is 
unobstructed and its clearance is adapted to the diameter of the rim of 
the core barrel and adjusted thereto during the repair of the primary 
shutdown controls, the crane of the reactor building remains free for the 
duration of the repair or replacement. Thus, for example, fuel elements 
can be repositioned in the meantime. The down time of the nuclear reactor 
is therefore greatly shortened in addition. 
Naturally, the sealing box can not only be used to evacuate certain 
conduits discharging into the reactor pressure vessel when the vessel is 
flooded, but also for the purpose of checking and repairing any desired 
wall areas of the reactor pressure vessel by various methods which would 
otherwise not be usable. Thus, not only can light sources and television 
cameras be lodged in the sealing box in order to view the covered wall 
areas, but remote controllable eddy current probes and devices for 
carrying out the color penetration method which could otherwise not be 
used in flooded wall sections, may also be installed in the sealing box. 
Lastly, the sealing box, which is already pressed firmly against the wall 
of the reactor pressure vessel as a result of hydrostatic pressure, offers 
a useful platform for operating remote controllable grinding, milling and 
welding machines in the sealing box. Thus, all kinds of repairs can be 
carried out under television control and without appreciable radiation 
exposure. In this connection, it is especially helpful if windows 54 to 
60, 61 and 62 are inserted in the wall of the sealing box 6, as indicated 
in FIGS. 1 and 3, for external observation by additional television 
cameras and/or light sources. 
In the repair fixture 4 shown as an example in FIGS. 1 to 3, the slide 
block 46 could be replaced by a hydraulic main cylinder. On the other 
hand, the two hydraulic cylinders 40, 41 responsible for the vertical 
displacement of the sealing box could be replaced by slide blocks 40a, 41a 
adapted to the local condition of the respective reactor type. The slide 
blocks raise the booms during pivoting as far as is appropriate for that 
reactor type. The positive guiding of the sealing box by slide blocks or 
guide cams prevents incorrect manipulations.