Fast neutron nuclear reactor comprising a suspended sealing slab and main vessel

A fast neutron nuclear reactor, in which the main vessel and the slab for sealing said vessel are separately suspended on the upper part of the vessel shaft. An outer ferrule of the slab is directly anchored in the vessel shaft by tie rods and is supported by an annular ring embedded in the concrete. The upper edge of the main vessel is welded beneath the ring, the vessel being supported by a second annular ring embedded in the concrete. The upper faces of the slab and the vessel shaft are consequently at the same level, thereby reducing the heights of the vessel shaft and the safety vessel.

BACKGROUND OF THE INVENTION 
The present invention relates to a fast neutron nuclear reactor of the type 
in which the reactor core is housed in a vessel, called the main vessel 
filled with liquid metal and sealed by a slab. More specifically, the 
invention relates to the supporting of the main vessel and the sealing 
slab by the upper part of the vessel shaft formed in the concrete 
enclosure for receiving the main vessel, in the case of a reactor of the 
aforementioned type. 
FIG. 1 is a diagrammatic cross-sectional view of a known, integrated fast 
neutron reactor. It is possible to see the concrete enclosure 10 defining 
the vessel shaft 12, in the upper part of which is hung the main vessel 14 
containing the reactor core 16. The latter rests on a supply support 18, 
which itself rests on the bottom of vessel 14 via flooring 20. 
The upper end of the main vessel 14 is sealed by a sealing slab 22 and 
contains the primary liquid metal 24, generally sodium. An inner vessel 26 
separates the sodium 24 in vessel 14 into two separate volumes. Thus, the 
inner vessel 26 respectively defines a hot collector 24a and a cold 
collector 24b. 
In its peripheral part, slab 22 supports a certain number of heat 
exchangers 28 and pumps 30. Under the action of pumps 30, the hot sodium 
leaving the reactor core 16 traverses the hot collector 24a prior to 
entering exchangers 28 through inlets 28a. The heat carried by the primary 
fluid is then transmitted to the secondary fluid. The cooled primary 
sodium leaves the exchangers through outlets 28b issuing into the cold 
collector 24b. It is then taken up by pumps 30 and is delivered to the 
supply support 18 of core 16 by pipes 32. Generally, the main vessel 14 is 
duplicated by a safety vessel 34, which is also suspended on the upper 
part of the vessel shaft. 
Fast neutron nuclear reactors of the loop type are distinguished from fast 
neutron reactors of the integrated type by the fact that the exchangers 
and optionally the pumps are no longer located within the main vessel and 
are instead positioned outside the latter. However, the operation of the 
reactor and the problems connected with the supporting of the vessel and 
the slab are the same. Therefore, the present invention can apply either 
to integrated or loop-type fast neutron reactors. 
FIG. 2 shows on a larger scale and in greater detail the supporting of 
vessels 14 and 34, as well as slab 22 by the upper part of the vessel 
shaft in the reactor of FIG. 1. It is clearly visible that the main vessel 
14 and sealing slab 22 are suspended in the upper part of the vessel shaft 
by a common support ferrule 36, which forms both the outer ferrule of the 
slab and the upper part of the main vessel 14. 
In this configuration, the attachment point 40 of the lower base plate 42 
of the slab to the upper part of vessel 14 must be positioned at a certain 
distance above the internal neutral gas atmosphere above the free sodium 
level of the main vessel 14 and must be thermally insulated from said 
atmosphere. Thus, if such a precaution is not taken, the upper part of the 
main vessel would be exposed to unacceptable thermal stresses resulting 
from the large temperature difference existing between the slab 22, cooled 
by a circulation of fluid diagrammatically represented by the arrows in 
FIG. 2, and the internal neutral gas atmosphere of the vessel 14. Thus, 
FIG. 2 shows that it is conventional practice to produce slab 22 in such a 
way that it has a downwardly projecting portion with respect to its 
attachment point 40 on the vessel. Thus, between vessel 14 and the lower 
base plate 42 of the slab, there is an annular zone 43, in which is placed 
a heat insulating material 44. 
Moreover, it is known that the thickness of slab 22 is determined, 
particularly with regards to its concrete filling, by a compromise between 
its neutron protection function and the criteria linked with its 
mechanical behaviour and cost. 
Thus, FIG. 2 shows that, according to the prior art, this compromise makes 
it necessary to place the upper base plate 46 of slab 22 at a lower level 
than the upper face of concrete enclosure 10. Thus, for a given 
dimensioning of the reactor block, if the thickness of the slab is 
approximately 2700 mm, this displacement reaches approximately 850 mm. 
As a result of this lowering of the upper level of the slab relative to the 
concrete enclosure surrounding it, any sodium leak occurring at the 
passage through the slab may lead to a sheet-like sodium fire thereon. The 
consequences of such a fire can be relatively serious, so that in existing 
structures, it is necessary to provide protection elements, such as one or 
more sodium retention tanks. 
Moreover, the downward displacement of the slab 22 relative to the upper 
face of the concrete enclosure 10 increases by the same amount the 
vertical dimensions of certain of the reactor components. In particular, 
the heights of the concrete enclosure 10, the safety vessel 34 and its 
thermal insulation are increased by this displacement. Other components, 
such as exchangers and handling locks consequently also have an increased 
height at the point of traversing the slab. This leads to an increase in 
the cost of the reactor. 
The present invention specifically relates to a fast neutron nuclear 
reactor, in which the main vessel and its sealing slab are separately 
suspended on the vessel shaft. This eliminates any displacement between 
the upper face of the slab and the upper case of the concrete enclosure 
surrounding it. This prevents any risk of sheet-like sodium fire on the 
slab, without it being necessary to use costly ancillary means. Moreover, 
the height of a certain number of reactor components is reduced by the 
height of the displacement of the slab relative to the upper face of the 
concrete enclosure which, in the aforementioned example, represents 
approximately 850 mm, which leads to a substantial reduction in the costs 
of the reactor. 
Thus, the invention relates to a fast neutron nuclear reactor comprising a 
liquid metal-filled main vessel containing the reactor core, a sealing 
slab which seals the vessel and a concrete enclosure defining a vessel 
shaft in which are located and suspended the main vessel and its sealing 
slab, wherein the slab and the main vessel are directly suspended on the 
upper part of the vessel shaft by separate supporting means. 
According to a preferred embodiment of the invention, the slab comprises a 
peripheral ferrule, whose upper end is anchored in the concrete enclosure 
in the upper part of the vessel wall by anchoring means, and a first 
horizontal support ring, provided with welded vertical stiffeners and 
whose inner periphery is welded, during production, in the vicinity of the 
upper end of the ferrule and whose outer periphery is sealed in the 
concrete enclosure below the anchoring means, the upper end of the main 
vessel being welded, following its installation in the vessel shaft, to 
the first support ring at a given distance from the peripheral ferrule of 
the slab, the supporting means for the main vessel also comprising a 
second horizontal support ring provided with vertical stiffeners and whose 
inner periphery is welded, during production, in the vicinity of the upper 
end of the main vessel and whose outer periphery is sealed in the concrete 
enclosure. 
When the reactor also comprises in per se known manner a safety vessel 
surrounding the main vessel, the safety vessel can be directly suspended 
in the upper part of the vessel shaft by supporting means separated from 
the supporting means for the main vessel and the supporting means for the 
slab. 
According to a preferred embodiment of the invention, the upper end of the 
safety vessel is welded, following installation in the vessel shaft, to 
the second support ring at a given distance from the main vessel, the 
supporting means for the safety vessel also comprising a third horizontal 
support ring, provided with vertical stiffeners and whose inner periphery 
is welded, during manufacture, to the safety vessel, in the vicinity of 
its upper end, said third support ring being sealed in the concrete 
enclosure. 
According to another appect of the invention, the slab has an upper portion 
laterally defined by a second ferrule, whose lower end is fixed to the 
peripheral ferrule below the first support ring, by means of a connecting 
ring, said ferrules defining between them an annular space housing a 
thermal insulating means, the upper face of the slab being substantially 
located in the same horizontal plane as the upper face of the concrete 
enclosure around the vessel shaft. 
In this case, the main vessel defines with the peripheral ferrule of the 
slab and with the upper end of the safety vessel, two annular spaces which 
can house heat insulating means, which are relatively tight to sodium 
leaks and compatible with the said liquid metal.

DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENT 
FIG. 3 shows the upper part of the vessel shaft 112 formed in the concrete 
enclosure 110 for receiving the main vessel 114, the safety vessel 134 and 
the sealing slab 122 of the vessel 114. This concrete part is cast 
following the installation and assembly of the supports of safety vessel 
134, main vessel 114 and slab 122. 
According to the invention, the main vessel 114, slab 122 and safety vessel 
134 are directly suspended on the upper part of the vessel shaft 112 by 
separate supporting means. 
Thus, th.e outer cylindrical ferrule 138 of slab 122 is directly anchored 
by its upper end to concrete enclosure 110, in the upper part of the 
vessel shaft 112. Slab 122 is supported by a horizontal support ring 152, 
provided with vertical stiffeners 153 (only one being visible in FIG. 3) 
and whose inner periphery is welded to ferrule 138. The outer part of ring 
152 is embedded in the concrete of enclosure 110. In practice and as shown 
in FIG. 3, this anchoring is completed by radial tie rods 148 embedded in 
the concrete of enclosure 110 and which traverse the ferrule 138, whilst 
being maintained in compression with ferrule 138 by nuts 149. The tie rods 
148 are arranged in a regular manner, e.g. every degree, over the 
periphery of the slab between the upper face 150 of that part of enclosure 
110 surrounding the vessel shaft 112 and the support ring 152. 
According to the invention, the main vessel 114 is suspended directly on 
enclosure 110 independently of slab 122. For this purpose, FIG. 3 shows 
that the cylindrical upper part of vessel 114 surrounds that part of 
ferrule 138 located below the support ring 152. Thus, between ferrule 138 
and the upper part of vessel 114 is defined an annular space 154, whose 
dimensions make it possible to obtain access to welds for any inspection 
which may be necessary in service. 
The outer upper edge of the main vessel 114 is welded, during assembly, to 
the lower face of support ring 152. Moreover, the outer face of vessel 114 
is welded, at a certain distance below horizontal ring 152, to a second 
horizontal support ring 156. As for ring 152, most of the ring 156 is 
sealed in the concrete of enclosure 110. 
The safety vessel 134 is also directly suspended on the upper part of the 
vessel shaft, independently of main vessel 114 and slab 122. 
For this purpose, the upper part of vessel 134 surrounds the upper part of 
vessel 114 located below the support ring 156. Thus, an annular space 158 
is formed between the upper parts of the two vessels. Like space 154, 
space 158 has a sufficient width to permit the inspection of welds. 
The outer upper edge of the safety vessel 32 is welded, during assembly, to 
the lower face of support ring 156. Moreover, the actual support of the 
safety vessel is produced by means of a third horizontal support ring 160, 
equipped with vertical stiffeners 161 (only one being visible in FIG. 3). 
For this purpose, the inner peripheral edge of ring 160 is welded, during 
manufacture, to the outer face of the upper cylindrical part of vessel 
134. As illustrated in FIG. 3, ring 160 is completely sealed into the 
concrete of enclosure 110. 
Safety vessel 134 has a frustum-shaped part 162, roughly level with the 
lower base plate 142 of slab 122. This part is extended downwards by the 
cylindrical wall of vessel 134, which constitutes the internal covering of 
vessel shaft 112 in the upper part of the latter. 
The safety vessel is anchored by means of vertical tie rods 164, fixed to 
the lower end of the frustum-shaped part 162, in the extension of the 
cylindrical wall of vessel 134. The tie rods 164 extend upwards to the 
vicinity of the upper face 150 of that part of enclosure 110 surrounding 
the vessel shaft and are embedded in the concrete of enclosure 110. Tie 
rods 164 are regularly distributed over the entire periphery of the vessel 
shaft and are e.g. spaced by two degrees. 
The assembly formed by the radial tie rods 148 and the vertical tie rods 
164 makes it possible to compensate the maximum torque of the support 
means for the vessels and the slab and to compressively stress the 
concrete of enclosure 110. 
In per se known manner, the anchoring means of ferrule 138 and the upper 
parts of vessel 114 and 134 in the concrete of enclosure 110 are 
supplemented by a large number of sealing lugs or tabs 166, fixed to said 
parts and sealed in the concrete of the vessel shaft. Like tie rods 164, 
these sealing tabs 166 are regularly distributed over the entire periphery 
of the vessel shaft, e.g. every two degrees. 
The vertical stiffeners 161, 157 and 153 are respectively welded to support 
rings 160, 156 and 152 as well as to the outer upper ends of safety vessel 
134, main vessel 114 and slab ferrule 138. 
As a result of the inventive use of separate support means for slab 122 and 
main vessel 114, the upper base plate 146 of slab 122 can be positioned at 
the same level or even higher than the upper face 150 of that part of 
enclosure 110 which surrounds the vessel shaft. Thus, a comparison of 
FIGS. 2 and 3 respectively illustrating the prior art and the present 
invention shows that that part of the slab projecting downwards within the 
main vessel in existing reactors is transferred according to the invention 
to the upper part of the slab, the total thickness thereof remaining 
unchanged. This modification to the structure of the slab is made possible 
by eliminating the welding of the lower base plate 142 of the slab to the 
main vessel 114. 
Moreover, the upper planar base plate 146 is connected to the outer ferrule 
138, below the support area thereof by concrete enclosure 110. This is 
Justified by the need to permit a thermal expansion of slab 122, whilst 
minimizing the thermal stresses of ferrule 138. 
In practice, this heightwise displacement between the upper base plate 146 
of slab 122 and its fixing point 168 to ferrule 138 is obtained in a 
manner comparable to the heightwise displacement between the lower base 
plate 42 and its fixing point 40 to the main vessel 14 according to the 
prior art shown in FIG. 2. 
Thus, the outer peripheral edge of the upper base plate 146 is welded to 
the upper edge of a coaxially arranged ferrule 170, which is at a certain 
distance within ferrule 138. The lower edge of ferrule 170 is welded to 
the inner peripheral edge at a horizontal ring 172, whose outer peripheral 
edge is welded at 168 to the interior of ferrule 138. Ring 172 is 
positioned approximately at the same level as ring 156. An upwardly open 
annular space 174 is consequently formed between the ferrules 170 and 138. 
The width of this space is conditioned by the access to the welds and its 
depth is a function of the admissible thermomechanical stresses for 
ferrule 138. The atmosphere in space 174 is the same as the atmosphere 
present in the reactor building (not shown) overhanging the slab and in 
general this atmosphere is air. 
To prevent sodium from a possible leak on the slab from coming into contact 
with the suspension ferrule 138, annular space 174, or at least the upper 
part thereof, is filled with an elastic insulating means 176. The latter 
is comparable to the means 44 insulating the fixing point 40 of the lower 
base plate 42 of the slab in the prior art and as illustrated in FIG. 2. 
Thus, means 176 can in particular be constructed according to the 
teachings of U.S. Pat. No. 3,995,918. However, means 176 can be more 
rudimentary and can in particular comprise mineral heat insulation, except 
in the upper part which has to resist the action and possible infiltration 
of liquid sodium. To complete the protection, a metal plate 178 obstructs 
a space 174 covering both part of the upper base plate 146 of the slab and 
part of the upper face 150 of the enclosure 110. 
As a result of the structure described hereinbefore, the receptacle formed 
above the slab as a result of the displacement existing in the prior art 
solutions between the upper base plate of the slab and the upper face of 
the concrete enclosure is eliminated. It is therefore possible to reduce, 
or even eliminate the protection against sodium fires on the slab, 
provided that ferrule 138 supporting the latter is protected. 
For a reactor having a given design and power, it is known that the depth 
of the main vessel from the lower base plate of the slab is clearly 
defined. Moreover, it has been seen that the thickness of the slab remains 
unchanged in this solution compared with the prior art. Thus, the height 
of a certain number of components of this reactor is reduced by the 
present invention. The value of this reduction corresponds to the 
elimination of the displacement existing in the prior art solutions 
between the upper base plate 46 of the slab and the upper face of the 
concrete enclosure. This height reduction resulting from the invention 
firstly relates to the civil engineering of the vessel shaft, the safety 
vessel 134 and its thermal insulation (not shown). It also relates to that 
part of the exchangers between the flanges by which they rest on the upper 
face of the slab and the outlet axes of the pipes of the secondary 
circuits, as well as the strut of the lock of the primary handling 
crossing and its ramp (not shown). 
Finally, compared with the prior art solutions, the mass of the protective 
concrete is increased in the lower part of the slab. The thermal inertia 
of this part of the slab is increased. The axial heat gradients are 
consequently reduced in the case of a cooling incident, particularly in 
the case of a lack of tension. 
Moreover, according to the invention, the upper parts of the main vessel 
and the slab are less thermally stressed as a result of the splitting up 
of the charges, particularly at their attachment point, which is close to 
the temperature of the vessel shaft. 
As illustrated in FIG. 3, the annular space 154 formed between the upper 
part of the main vessel 114 and the outer ferrule 138 of the slab is 
closed at its base by the combination of a metal thermal insulation 180 
engaged with the vessel and an elastic insulating means 182, which make it 
possible to prevent convective neutral gas rises. In order to complete the 
sealing of the annular space 154, an insulating means 183, which is 
thicker than insulating means 182, is located beneath the latter and is 
held against the lower part of the metal heat insulation 180 by a ferrule 
186 welded to the base plate 142 of slab 122, as well as plates 188 which 
are welded, after fitting the thermal insulation, to ferrule 186. The 
thermal insulation 180 and the elastic insulating means 182,183 are 
produced in per se known manner, e.g. according to U.S. Pat. Nos. 
4,022,657 and 4,055,464. 
In a comparable manner, the space 158 formed between the upper parts of 
vessels 114 and 134 can be closed at its base by an elastic insulating 
means 184 similar to means 182. 
The structure of the actual slab does not form part of the present 
invention and will consequently not be described herein. It should be 
simply noted that slab 122, as is partly shown in FIG. 3, is preferably 
constructed according to U.S. Pat. No. 4,464,334. However, any other 
structure could be envisaged without passing outside the scope of the 
invention. 
According to the invention, the assemblies formed by the main vessel 114 
and its support ring 56, provided with stiffeners 161, slab 122 and its 
support ring 152, provided with stiffeners 153 and the upper part of 
safety vessel 134 and its support ring 160, provided with stiffeners 161 
can be entirely manufactured in the workshop on the site of the reactor 
during the construction of the latter. Compared with the prior art 
solutions, this eliminates the difficult operation of homogeneous welding 
between the main vessel and the upper part of the vessel carried out 
inside the reactor block. The presence of the support ring also makes it 
easier to handle the vessel.