GB1567264A - Liquid metal cooled fast breeder nuclear reactors - Google Patents
Liquid metal cooled fast breeder nuclear reactors Download PDFInfo
- Publication number
- GB1567264A GB1567264A GB6301/77A GB630177A GB1567264A GB 1567264 A GB1567264 A GB 1567264A GB 6301/77 A GB6301/77 A GB 6301/77A GB 630177 A GB630177 A GB 630177A GB 1567264 A GB1567264 A GB 1567264A
- Authority
- GB
- United Kingdom
- Prior art keywords
- cruciform
- panels
- coolant
- strips
- barrier
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired
Links
- 229910001338 liquidmetal Inorganic materials 0.000 title claims description 17
- 239000002826 coolant Substances 0.000 claims description 50
- 230000004888 barrier function Effects 0.000 claims description 31
- 239000012528 membrane Substances 0.000 claims description 20
- 238000009413 insulation Methods 0.000 claims description 19
- 125000006850 spacer group Chemical group 0.000 claims description 10
- 238000001816 cooling Methods 0.000 claims description 7
- 238000007789 sealing Methods 0.000 claims description 6
- 239000012530 fluid Substances 0.000 claims description 3
- 239000000463 material Substances 0.000 claims description 3
- 238000006073 displacement reaction Methods 0.000 claims description 2
- 210000004379 membrane Anatomy 0.000 description 16
- 238000010276 construction Methods 0.000 description 9
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 8
- 229910052708 sodium Inorganic materials 0.000 description 8
- 239000011734 sodium Substances 0.000 description 8
- 230000035882 stress Effects 0.000 description 4
- 239000007788 liquid Substances 0.000 description 3
- 238000004519 manufacturing process Methods 0.000 description 2
- 230000003068 static effect Effects 0.000 description 2
- 241000167857 Bourreria Species 0.000 description 1
- 241000196324 Embryophyta Species 0.000 description 1
- 230000015556 catabolic process Effects 0.000 description 1
- 238000006731 degradation reaction Methods 0.000 description 1
- 230000001788 irregular Effects 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 230000000717 retained effect Effects 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 230000008646 thermal stress Effects 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C11/00—Shielding structurally associated with the reactor
- G21C11/08—Thermal shields; Thermal linings, i.e. for dissipating heat from gamma radiation which would otherwise heat an outer biological shield ; Thermal insulation
- G21C11/083—Thermal shields; Thermal linings, i.e. for dissipating heat from gamma radiation which would otherwise heat an outer biological shield ; Thermal insulation consisting of one or more metallic layers
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C11/00—Shielding structurally associated with the reactor
- G21C11/08—Thermal shields; Thermal linings, i.e. for dissipating heat from gamma radiation which would otherwise heat an outer biological shield ; Thermal insulation
- G21C11/088—Thermal shields; Thermal linings, i.e. for dissipating heat from gamma radiation which would otherwise heat an outer biological shield ; Thermal insulation consisting of a stagnant or a circulating fluid
-
- 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
Landscapes
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Health & Medical Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- Biomedical Technology (AREA)
- General Health & Medical Sciences (AREA)
- Molecular Biology (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Description
(54) LIQUID METAL COOLED FAST BREEDER NUCLEAR REACTORS
(71) We, NUCLEAR POWER COMPANY
LIMITED, of of 1, Stanhope Gate, London,
W1A 1EH, a British Company, do hereby declare the invention, for which we pray that a patent may be granted to us, and the method by which it is to be performed, to be particularly described in and by the following statement: This invention relates to liquid metal cooled fast breeder nuclear reactors.
In one known construction of liquid metal cooled fast breeder nuclear reactor the reactor core is submerged in a pool of liquid metal coolant in a primary vessel which is
housed in a concrete vault. The core is carried by a strong back and is surrounded by an impermeable barrier bounding an inner or hot region of the pool and an outer or cool region of the pool. There is a plurality of coolant pumps in the outer region which circulate coolant upwardly through the core by way of the strongback thence to a plurality of heat exchangers in the hot region which discharge to the cool region.
In order that the diameter of the primary vessel and therefore the magnitude of the concrete vault shall be as small as possible.
the pumps and heat exchangers are arranged alternately and generally side-by-side in the primary vessel and the barrier has un
dulating contours to enable it to pass between them. As the temperature of the inner pool is approximately 5400C and that of the outer pool is approximately 370"C thermal insulation is provided on the hot side of the barrier to reduce temperature degradation of the inner pool and to reduce thermal stresses induced in the barrier. However, because there is a pressure differential across the barrier during operation of the reactor the barrier is constructed to pressure vessel standards but design and manufacture to meet such exacting standards is made very difficult because of the irregular shape and the complexity of the many induced stresses.
It is an object of the invention to provide a construction of liquid metal cooled fast breeder nuclear reactor in which the complexity of design and manufacture of a barrier for bounding inner and outer pools of coolant is reduced.
According to the invention in a liquid metal cooled fast breeder nuclear reactor of the kind comprising a nuclear reactor core submerged in a pool of coolant within a primary vessel and having a barrier surrounding the core and bounding inner and outer regions of the pool, a coolant pump in the outer region for circulating coolant through the core and through a heat exchanger disposed in the inner region, the barrier is permeable and comprises a thermally insulating medium and the upper region of the barrier is surrounded by a continuous impermeable membrane spaced from the barrier, the interspace forming a cooling jacket and having coolant flow ducts extending through it.
In a preferred construction the coolant flow ducts extending through the interspace comprise a continuous rank of upstanding pipes connected at their lower ends to a header which is fed with coolant by the coolant pump, the upper ends of the pipes opening into capping thimbles which extend over the depth of the membrane. The coolant pipes are in heat exchange with pool coolant flooding the interspace thereby creating the cooling jacket.
From another aspect the invention can be said to reside in a liquid metal cooled fast breeder nuclear reactor wherein the conventional inner tank constituting a fluid tight barrier for defining the inner and outer regions of the pool and for supporting the thermal insulation is dispensed with, the inner tank being replaced by a permeable thermal insulation supporting skeletal framework which is not subject to complex stresses caused by large temperature differentials.
In a preferred construction the thermal insulation medium is of the kind disclosed in a co-pending application of the same date by Hodgsoo Howard, Dale and Hall. The insulating medium comprises a plurality of spaced layers of sheet material, each layer lying substantially parallel to a supporting skeletal framework and comprising rectilinear panels secured to the framework in spaced array in vertical and horizontal rows, and closure members for the spaces therebetween, the closure members being of cruciform shape and the arms thereof being arranged to overlap opposed faces of adjacent panels.
Thermally insulating medium of this kind although permeable forms a substantial barrier to flowing coolant and has adequate clearances distributed over the area of the layers to allow superficial thermal expansion to take place without causing distortion of the layers or setting up complex stresses. In the event of failure of the attachment of a panel to the frame the released panel is retained in position by the adjoining panels and strips thus providing for reliability in service.
A construction of liquid metal cooled fast breeder nuclear reactor according to the invention is described, by way of example only, with reference to the drawings accompanying the Provisional Specification wherein,
Figure 1 is a sectional view of the construction,
Figure 2 is a fragmentary plan view, partly in cross-section of the construction of Figure 1,
Figure 3 is a fragmentary sectional view on line 111-111 of Figure 2,
Figure 4 is a fragmentary front view of thermal insulation used in the construction of Figure a framentary plan view 1, Figure 5 is a fragmentary plan view in section on line V-V of Figure 4; and
Figure 6 is a fragmentary plan view in section on line VI-VI of Figure 4.
In the construction shown in Figure 1 the
reactor core 1 is submerged in a pool of liquid sodium coolant 2 in a primary vessel 3 which is housed in a concrete vault 4. The core is carried by a strongback 5 and is surrounded by a barrier 6 which bounds inner and outer regions 7, 8 of the pool.
There are eight coolant pumps 9 (only one being shown in Figure 1) in the outer region 8 for circulating coolant though the core by way of the strongback 5 and thence to eight heat exchangers 10 (again only one being shown in Figure 1) disposed in the inner region 7. The heat exchangers finally discharge the coolant into the outer region.
The primary vessel 3, a leak jacket 11 for the primary vessel, the strongback 5, heat exchangers 10 and coolant pumps 9 are all suspended from the roof of the vault and the roof includes a double rotating shield
12 from which control rods 13 extend to
the top of the core. A neutron shield 15 surrounds the core within the barrier 6 which is described in greater detail hereinafter. A secondary liquid sodium coolant flowing through the heat exchangers conveys the heat energy derived from the core to steam generating plant not shown in the drawings.
In operation of the reactor, the coolant in the inner region of the pool is at temperature approximately 540"C and that in the outer region is at temperature approximately 3700C. The pressure differential across the inlet and outlet ports of the pumps 9 causes a differential in the levels of the coolant in the regions the levels being designated L1 and L2.
Referring now to Figure 2 which shows in plan view, in a 900 sector, some details of the layout of the heat exchangers 10, coolant pumps 9 and barrier 6, there is a skeletal framework 14 upstanding from the strongback 5. The framework 14 embraces the coolant pumps 9 and supports thermal insulation forming the barrier 6. There is also a continuous flow baffle 17 which partly embraces each heat exchanger 10.
The barrier forming thermal insulation comprises a plurality of spaced layers of stainless steel sheet 18 defining a radial series of compartments 19 for containing substantially static sodium. The upper region of the barrier 6 is surrounded by a continuous impermeable membrane 20 extending downwardly and as shown in Figure 3 spaced from the insulation to form a cooling jacket 21 for the continuous membrane. A continuous rank of coolant conducting pipes 22 connected at their lower ends to a header (not shown) at strongback level is fed with coolant from the coolant pumps, the pipes extending upwardly between the thermal insulation and the continuous membrane 20.
Each coolant pipe 22 is reduced in diameter over the upper part of its length co-extensive with the membrane 20 and the open upper end has a capping thimble 23 extending downwardly over the depth of the continuous membrane 20.
In use of the reactor, sodium flooding the compartments 19 formed by the membranes 18 of the insulation is substantially static thereby providing a resistance to heat transfer between the inner and outer regions of the pool of coolant. However, owing to the difference in levels L1, L2 of the inner and outer pool level by the continuous mem brane 20, there is no heat transfer across the membrane over the differential levels between the inner pool sodium and the sodium in the outer pool so that supplementary cooling means is required for the continuous membrane. The supplementary cooling means is provided by cool liquid sodium flowing from the outer pool upwardly through the pipes 22 then downwardly through the capping thimbles 23 in heat exchange with sodium flooding the interspace between continuous membrane and thermal insulation. Instead of the coolant being supplied to the header by the pumps 9 it may, alternatively, be supplied by electromagnetic pumps.
Referring now to Figures 4, 5 and 6 the thermal insulation comprises rectilinear panels 24 secured to the framework 14 by
central retaining studs 25. The panels 24 are spaced apart and arranged in vertical and horizontal rows. The spaces between the panels are closed by closure members 18 also secured to the framework 14 by studs 25. The closure members 18 are of cruciform shape each comprising a cruciform spacer 27 intermediate a pair of cruciform sealing strips 26. The inner (relative to the clad side of the framework) cruciform strip 26 of each member is welded to the spacer 27 whilst the outer is free for assembly after placing the complementing panel 24. The sealing strips 26 of each member 18 are disposed to overlap opposed faces of a panel 24 and each arm of the cruciform member co-operates with an arm of a neighbouring cruciform member to extend along and overlap adjacent sides of adjacent panels. The combination of cruciform strips 26, spacer
27 and panel 24 form a labyrinth barrier serving to restrict flow of coolant through each layer of panels. The studs 25 are arranged in two lattices of square pitch, one lattice being displaced relative to the other
by one half pitch in both horizontal and vertical directions and each stud carries alternately a panel 24 and a closure member
18 so that the vertical rows of panels in one layer are displaced relative to the vertical rows of panels in an adjacent layer, the displacement being one half of the pitch of the rows in both horizontal and vertical directions. By displacing the panels in one layer relative to the panels in an adjacent layer
coolant flow across the insulation due to convection currents is reduced.
The panels are 0.9 metre square and 0.55
mm thick and are disposed on a 1 metre square lattice pitch. The cruciform strips of the sealing members are 0.55 mm thick and the cruciform spacing members are 0.70 mm thick. Stud spacers 29 10 mm thick serve to space the closure members.
A clearance 32 is provided between the cnds of the arms of the cruciform strips to provide for thermal expansion but the joints are closed to fluid flow by lapping strips 30 attached to selected arms of the cruciform strips. Two of the arms of each spacer 27 are longer than the other two, long and short arms of adjoining strips being assembled together and providing an expansion clearance 33 which is displaced from the expansion clearance 32 of the strips. pacers 31 are also attached to selected arms of the cruciform strips to hold adjacent strips of adjacent membranes in place.
Thermal insulation of the described form provides a substantial barrier to flow of coolant and accommodates both lateral and longitudinal expansion. The expansion is absorbed gradually over a small area of a membrane and thereby substantially avoids distortion and complex stresses. The insulation is easily erected because the components are small and can be handled by an operator and components can be readily repaired or replaced on site.
WHAT WE CLAIM IS:- 1. A liquid metal cooled fast breeder nuclear reactor of the kind comprising a nuclear reactor core submerged in a pool of coolant within a primary vessel and having a barrier surrounding the core and bounding inner and outer regions of the pool there being a coolant pump in the outer region for circulating coolant through the core and through a heat exchanger disposed in the inner region wherein the barrier is permeable and comprises a thermally insulating medium and the upper region of the barrier is surrounded by a continuous impermeable membrane spaced from the barrier, the interspace forming a cooling jacket and having coolant flow ducts extending through it.
2. A liquid metal cooled fast breeder nuclear reactor according to claim 1 wherein the coolant flow ducts extending through the interspace comprise a continuous rank of upstanding pipes connected at their lower ends to a header which is fed with coolant by the coolant pump, the upper ends of the pipes opening into capping thimbles which extend over the depth of the membrane.
3. A liquid metal cooled fast breeder nuclear reactor according to either of claims 1 and 2 wherein the insulating medium comprises a plurality of spaced layers of sheet material each layer lying substantially parallel to a supporting skeletal framework and comprising rectilinear panels secured to the framework in spaced array in vertical and horizontal rows, and closure members for the spaces therebetween, the closure members being of cruciform shape and the arms thereof being arranged to overlap opposed faces of adjacent panels.
4. A liquid metal cooled fast breeder nuclear reactor substantially as hereinbefore described with reference to the drawings accompanying the Provisional Specification.
**WARNING** end of DESC field may overlap start of CLMS **.
Claims (4)
- **WARNING** start of CLMS field may overlap end of DESC **.being supplied to the header by the pumps 9 it may, alternatively, be supplied by electromagnetic pumps.Referring now to Figures 4, 5 and 6 the thermal insulation comprises rectilinear panels 24 secured to the framework 14 by central retaining studs 25. The panels 24 are spaced apart and arranged in vertical and horizontal rows. The spaces between the panels are closed by closure members 18 also secured to the framework 14 by studs 25. The closure members 18 are of cruciform shape each comprising a cruciform spacer 27 intermediate a pair of cruciform sealing strips 26. The inner (relative to the clad side of the framework) cruciform strip 26 of each member is welded to the spacer 27 whilst the outer is free for assembly after placing the complementing panel 24. The sealing strips 26 of each member 18 are disposed to overlap opposed faces of a panel 24 and each arm of the cruciform member co-operates with an arm of a neighbouring cruciform member to extend along and overlap adjacent sides of adjacent panels. The combination of cruciform strips 26, spacer27 and panel 24 form a labyrinth barrier serving to restrict flow of coolant through each layer of panels. The studs 25 are arranged in two lattices of square pitch, one lattice being displaced relative to the other by one half pitch in both horizontal and vertical directions and each stud carries alternately a panel 24 and a closure member18 so that the vertical rows of panels in one layer are displaced relative to the vertical rows of panels in an adjacent layer, the displacement being one half of the pitch of the rows in both horizontal and vertical directions. By displacing the panels in one layer relative to the panels in an adjacent layer coolant flow across the insulation due to convection currents is reduced.The panels are 0.9 metre square and 0.55 mm thick and are disposed on a 1 metre square lattice pitch. The cruciform strips of the sealing members are 0.55 mm thick and the cruciform spacing members are 0.70 mm thick. Stud spacers 29 10 mm thick serve to space the closure members.A clearance 32 is provided between the cnds of the arms of the cruciform strips to provide for thermal expansion but the joints are closed to fluid flow by lapping strips 30 attached to selected arms of the cruciform strips. Two of the arms of each spacer 27 are longer than the other two, long and short arms of adjoining strips being assembled together and providing an expansion clearance 33 which is displaced from the expansion clearance 32 of the strips. pacers 31 are also attached to selected arms of the cruciform strips to hold adjacent strips of adjacent membranes in place.Thermal insulation of the described form provides a substantial barrier to flow of coolant and accommodates both lateral and longitudinal expansion. The expansion is absorbed gradually over a small area of a membrane and thereby substantially avoids distortion and complex stresses. The insulation is easily erected because the components are small and can be handled by an operator and components can be readily repaired or replaced on site.WHAT WE CLAIM IS:- 1. A liquid metal cooled fast breeder nuclear reactor of the kind comprising a nuclear reactor core submerged in a pool of coolant within a primary vessel and having a barrier surrounding the core and bounding inner and outer regions of the pool there being a coolant pump in the outer region for circulating coolant through the core and through a heat exchanger disposed in the inner region wherein the barrier is permeable and comprises a thermally insulating medium and the upper region of the barrier is surrounded by a continuous impermeable membrane spaced from the barrier, the interspace forming a cooling jacket and having coolant flow ducts extending through it.
- 2. A liquid metal cooled fast breeder nuclear reactor according to claim 1 wherein the coolant flow ducts extending through the interspace comprise a continuous rank of upstanding pipes connected at their lower ends to a header which is fed with coolant by the coolant pump, the upper ends of the pipes opening into capping thimbles which extend over the depth of the membrane.
- 3. A liquid metal cooled fast breeder nuclear reactor according to either of claims 1 and 2 wherein the insulating medium comprises a plurality of spaced layers of sheet material each layer lying substantially parallel to a supporting skeletal framework and comprising rectilinear panels secured to the framework in spaced array in vertical and horizontal rows, and closure members for the spaces therebetween, the closure members being of cruciform shape and the arms thereof being arranged to overlap opposed faces of adjacent panels.
- 4. A liquid metal cooled fast breeder nuclear reactor substantially as hereinbefore described with reference to the drawings accompanying the Provisional Specification.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB6301/77A GB1567264A (en) | 1978-01-18 | 1978-01-18 | Liquid metal cooled fast breeder nuclear reactors |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB6301/77A GB1567264A (en) | 1978-01-18 | 1978-01-18 | Liquid metal cooled fast breeder nuclear reactors |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1567264A true GB1567264A (en) | 1980-05-14 |
Family
ID=9812005
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB6301/77A Expired GB1567264A (en) | 1978-01-18 | 1978-01-18 | Liquid metal cooled fast breeder nuclear reactors |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB1567264A (en) |
-
1978
- 1978-01-18 GB GB6301/77A patent/GB1567264A/en not_active Expired
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed | ||
PCNP | Patent ceased through non-payment of renewal fee |