GB1597189A - Nuclear reactor fuel sub-assemblies - Google Patents
Nuclear reactor fuel sub-assemblies Download PDFInfo
- Publication number
- GB1597189A GB1597189A GB20581/78A GB2058178A GB1597189A GB 1597189 A GB1597189 A GB 1597189A GB 20581/78 A GB20581/78 A GB 20581/78A GB 2058178 A GB2058178 A GB 2058178A GB 1597189 A GB1597189 A GB 1597189A
- Authority
- GB
- United Kingdom
- Prior art keywords
- fuel
- wrapper
- pins
- hold down
- cellular
- 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
- 238000000429 assembly Methods 0.000 title claims description 6
- 239000003758 nuclear fuel Substances 0.000 title description 3
- 239000000446 fuel Substances 0.000 claims description 70
- 230000001413 cellular effect Effects 0.000 claims description 32
- 239000002826 coolant Substances 0.000 claims description 19
- 238000010276 construction Methods 0.000 claims description 14
- 238000000034 method Methods 0.000 claims description 12
- 229910001338 liquidmetal Inorganic materials 0.000 claims description 10
- 230000000717 retained effect Effects 0.000 claims description 10
- 239000007788 liquid Substances 0.000 claims description 7
- 238000012958 reprocessing Methods 0.000 claims description 4
- 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 claims description 2
- 229910052708 sodium Inorganic materials 0.000 claims description 2
- 239000011734 sodium Substances 0.000 claims description 2
- 229910000831 Steel Inorganic materials 0.000 description 2
- 238000006073 displacement reaction Methods 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 239000010959 steel Substances 0.000 description 2
- 229910052778 Plutonium Inorganic materials 0.000 description 1
- 239000012634 fragment Substances 0.000 description 1
- 238000005339 levitation Methods 0.000 description 1
- 239000008188 pellet Substances 0.000 description 1
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/33—Supporting or hanging of elements in the bundle; Means forming part of the bundle for inserting it into, or removing it from, the core; Means for coupling adjacent bundles
- G21C3/331—Comprising hold-down means, e.g. springs
-
- 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
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
(54) NUCLEAR REACTOR FUEL SUB-ASSEMBLIES
(71) We, UNITED KINGDOM ATOMIC
ENERGY AUTHORITY, London, a British Authority, 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 fuel sub-assemblies for liquid metal cooled fast breeder nuclear reactors.
A fuel sub-assembly for a liquid metal cooled fast breeder nuclear reactor comprises a bundle of spaced fuel pins within a tubular wrapper or sleeve through which liquid metal coolant can be flowed in heat exchange with the fuel pins. The pins may be spaced by a series of cellular grids attached to the wrapper each pin occupying a discrete cell of each grid and the wrapper has a spiked extension at one end (hereinafter termed the lower end) whereby the sub-assembly can be located in a support structure and arranged with other sub-assemblies to upstand in sideby-side array to form a fuel assembly. The upper end of the wrapper is extended by a tubular neutron shield of massive steel. In
Patent No 1.478.985 there is disclosed a nuclear reactor fuel element sub-assembly comprising a bundle of spaced parallel fuel pins within a tubular wrapper, the pins having peripherally enlarged heads at one end portion and the heads being captive between a fixed end abutment grid and a fixed cellular grid. the one end portion of each pin being formed with coolant flow passages. In the disclosed fuel sub-assembly one end of each fuel pin is held captive between a fixed end abutment grid and a fixed cellular hold down grid so that axial displacement of the pins is prevented without restricting the pins ability to expand longitudinally. After irradiation of a fast breeder sub-assembly it is necessary to reprocess it to recover unused fissile material and to separate newly formed plutonium from the residues but because of irradiation embrittlement of the pins dismantling of the subassembly is difficult. Prior to the present invention the technique used for dismantling a fuel sub-assembly has been to remove the lower end spike extension and end abutment grid from the wrapper and then carefully to withdraw the fuel pins one by one for reprocessing but as the operation must be carried out by remote control because of radioactivity it is a time consuming and expensive process.
One object of the present invention is to provide a fuel sub-assembly for a liquid metal cooled fast breeder nuclear reactor of such construction that it will facilitate dismantling for reprocessing purposes and another object is to provide an improved method of dismantling a fuel sub-assembly.
According to the invention a fuel subassembly for a liquid metal cooled fast breeder nuclear reactor comprises a bundle of fuel pins within a tubular wrapper and spaced apart by a series of compliant cellular bracing grids (as defined hereinafter) each pin occupying a discrete cell of each grid, the wrapper having a lower end spike extension and an upper end tubular neutron shield extension and wherein the pins are each retained at one end by a cellular hold down grid (as defined hereinafter) which is secured to an end region of the tubular wrapper.
Conveniently, the pins may be retained at their lower ends by a cellular hold down grid which is secured to the lower end region of the tubular wrapper.
By "compliant cellular bracing grid" is meant a grid of honeycomb construction wherein each cell has resiliently yieldable contact pads for slidably guiding a fuel pin, the pads being arranged in a first set which normally brace the pin co-axially within its cell and a second set which, though normally clear of the pins, provides a second brace in the event of excessive displacement of the pads of the first set. By "cellular hold down grid" is meant a grid having means for retainably engaging ends of the pins thereby to prevent withdrawal of the pins from the cells of the grid during normal operation of the nuclear reactor. In a preferred construction of sub-assembly according to the invention the lower end of each pin has a radial projection for abutting the underside of the hold down grid.
A fuel sub-assembly according to the invention can be easily dismantled by severing the end regions of the wrapper immediately below the tubular neutron shield and immediately above the spike extension followed by severing of the wrapper immediately above the hold down grid so that the hold down grid with a fragment of the wrapper and the complete bundle of fuel pins can be withdrawn from the remnants of the wrapper. The compliant nature of the grids facilitates withdrawal of the pins from the series of bracing grids and thereby reduces fracture of the embrittled pins.
The invention will also reside in a method of dismantling a fuel sub-assembly comprising a bundle of fuel pins within a tubular wrapper and spaced apart by a series of compliant cellular bracing grids (as defined hereinbefore). the wrapper having a lower end spike extension and an upper end tubular neutron shield extension and wherein the pins are retained at their lower ends by a cellular hold down grid (as defined hereinbefore) which is secured to the lower end region of the tubular wrapper, the method comprising the steps of severing the upper and lower end regions of the wrapper to separate the tubular neutron shield and spike extensions from the wrapper, severing the wrapper immediately above the cellular hold down grid and withdrawing the combination of hold down grid and bundle of fuel pins from the combination of wrapper and series of bracing grids.
Constructions of fuel sub-assemblies embodying the invention for use in a fast breeder liquid metal-cooled nuclear reactor are described by way of example with reference to the accompanying drawings wherein
Figure 1 is a diagrammatic sectional view of a typical fuel sub-assembly,
Figure 2 is a fragmentary sectional view of one construction according to the invention,
Figure 3 is a fragmentary cross-sectional view on line 111III of Figure 2,
Figure 4 is a fragmentary sectional view of an alternative construction of fuel sub-assembly.
Figure 5 is a diagrammatic view of an alternative feature for a fuel sub-assembly generally similar to those shown in Figures 2 and 4,
Figure 6 is an isometric view of a discrete cell of a compliant cellular grid, and
Figure 7 is a diagrammatic sectional view of a liquid metal-cooled fast breeder nuclear reactor.
A fuel sub-assembly as shown in Figure 1 for a liquid metal-cooled fast breeder nuclear reactor comprises a central fuel section 1, a lower end locating section 2 and an upper end neutron shielding section 3. The fuel section I comprises a bundle of 325 elongate fuel pins 4 enclosed within a tubular wrapper 5 of hexagonal cross-section and are spaced apart by a series of compliant cellular bracing grids 6 each pin occupying a discrete cell of each grid. The cellular grids 6 are welded to the wrapper 5 and the fuel pins 4 are supported within the wrapper at their lower ends by an abutment grid 7. The fuel pins 4 are retained at their lower ends by a cellular hold down grid 7a which is secured to the lower end region of the tubular wrapper 5.
The lower end locating section 2 comprises a spike extension 8 for engaging sockets in a fuel assembly support structure 9 and has apertures 10 through which coolant can flow from within the diagrid. The upper section 3 is of massive steel and comprises a tubular member 11 having an extension 12 with an internal lip 13 for engagement by lifting means.
Referring now to Figures 2 and 3, each fuel pin comprises a stack of fuel pellets sheathed by a stainless steel tube 14 which is sealably closed by each end by plugs 15 and each pin has a lower end overcap 16 which engages a cell of the hold down grid 7a. The overcap 16 is centrally positioned within the cell by 3 equally angularly spaced pads 17 so that there is a clear passage about the overcap for upward flow of liquid metal coolant. The overcap carried a hook which provides a radial projection 18 lying intermediate the hold down grid 7a and the abutment grid 7.
During transportation of the fuel subassembly, the fuel pins are supported at their lower ends by the abutment grid 7 and during normal operation of the nuclear reactor, the pins are restrained against levitation by upward flow of coolant by abutment of the hooks 18 with the underside of the hold down grid 7a.
The compliant cellular bracing grids 6 are of the kind disclosed in UK Patent Application GB 2011150 A each of which has a right hexagonal boundary and comprises 325 unit cells arranged in honeycomb pattern, the cells being generally of hexagonal shape as shown in Figure 6. Each unit cell is formed from strip material and three sides have a rectangular window 33 whilst the three alternating sides each have an elongate embossment or dimple 34 the dimples forming a guide pad for a fuel pin. There is a pair of smaller embossments 35 disposed one beyond each end of the elongate embossments and which provide additional bracing pads or backstops for a fuel pin in the event that bowing of the pin occurs during irradiation of the fuel sub-assembly. Each pair of abutting sides of the cells are secured together by a pair of spot welds disposed in opposed end regions of the sides. A compliant grid of this nature enables the pins to be slidably guided with the minimum of bearing loading whilst the backstop pads 35 provide adequate bearing loading to resist irradiation bowing of the pins.
For reprocessing purposes after irradiation of the fuel sub-assembly, the wrapper is separated from the lower end locating section 2 and the upper end neutron shielding section 3 by severing the upper and lower end regions of the wrapper, then the wrapper is severed again immediately above the hold down grid 7a. The entire fuel pin bundle and hold down grid combination can then be withdrawn from the wrapper 5 and cellular grids 6 combination in one operation, the withdrawal operation being made possible by the compliant nature of the cellular grids 6.
In the alternative construction shown in
Figure 4, the radial projection 18 takes the form of an eye 19 whilst in the construction shown in Figure 5, the radial projection 18 is a flange generally of triangular form. In each of the constructions, the radial projection is of a form which offers little restriction to the coolant flow passages through the hold down grid 7a.
The described fuel sub-assemblies are used in a liquid metal-cooled fast breeder reacton of the pool kind shown in Figure 7. The construction comprises a fuel assembly 21 submerged in a pool 22 of liquid sodium coolant in a primary vessel 23. The primary vessel is suspended from the roof of the containment vault 24 and there is provided a plurality of coolant pumps 25 and heat exchangers 26 only one of each of pump and heat exchangers being shown. The fuel assembly 21 mounted on a support member 27 is housed with the heat exchangers- in a core tank 28 whilst the pumps 25 which deliver coolant to the support member are disposed outside of the core tank. Control rods 29 and instrumentation 30 penetrate the roof of the vault.
In operation, relatively cold coolant is drawn from the pool outside the core tank 28 and passed upwardly through the fuel assembly by way of the support member 27 and then flows through the heat exchanger 26 in heat exchange e with a second coolant which flows through steam generating plant disposed outside of the vault. The main coolant is returned from the heat exchanger to the outer region of the pooi.
WHAT WE CLAIM IS:
1. A fuel sub-assembly for a liquid metal cooled fast breeder nuclear reactor comprising a bundle of fuel pins within a tubular wrapper and spaced apart by a series of compliant cellular bracing grids (as defined hereinbefore) each pin occupying a discrete cell of each grid, the wrapper having a lower end spike extension and an upper.end tubular neutron shield extension and wherein the pins are each retained at one end by a cellular hold down grid (as defined hereinbefore) which is secured to an end region of the tubular wrapper.
2. A fuel sub-assembly according to claim 1 wherein the pins are retained at their lower ends by a cellular hold down grid which is secured to the lower end region of the tubular wrapper.
3. A fuel sub-assembly according to claim 2 wherein the lower end of each pin has a radial projection for abutting the underside of the hold down grid.
4. A method of dismantling a fuel subassembly comprising a bundle of fuel pins within a tubular wrapper and spaced apart by a series of compliant cellular bracing grids (as defined hereinbefore), the wrapper having a lower end spike extension and an upper end tubular neutron shield extension and wherein the pins are retained at their lower ends by a cellular hold down grid (as defined hereinbefore) which is secured to the lower end region of the tubular wrapper, the method comprising the steps of severing the upper and lower end regions of the wrapper to separate the tubular neutron shield and spike extension from the wrapper, severing the wrapper immediately above the cellular hold down grid and withdrawing the combination of hold down grid and bundle of fuel pins from the combination of wrapper and series of bracing grids.
5. A fuel sub-assembly for a liquid metal cooled fast breeder nuclear reactor substantially as hereinbefore described with reference to the accompanying drawings.
6. A method of dismantling a fuel subassembly substantially as hereinbefore described.
**WARNING** end of DESC field may overlap start of CLMS **.
Claims (6)
1. A fuel sub-assembly for a liquid metal cooled fast breeder nuclear reactor comprising a bundle of fuel pins within a tubular wrapper and spaced apart by a series of compliant cellular bracing grids (as defined hereinbefore) each pin occupying a discrete cell of each grid, the wrapper having a lower end spike extension and an upper.end tubular neutron shield extension and wherein the pins are each retained at one end by a cellular hold down grid (as defined hereinbefore) which is secured to an end region of the tubular wrapper.
2. A fuel sub-assembly according to claim 1 wherein the pins are retained at their lower ends by a cellular hold down grid which is secured to the lower end region of the tubular wrapper.
3. A fuel sub-assembly according to claim 2 wherein the lower end of each pin has a radial projection for abutting the underside of the hold down grid.
4. A method of dismantling a fuel subassembly comprising a bundle of fuel pins within a tubular wrapper and spaced apart by a series of compliant cellular bracing grids (as defined hereinbefore), the wrapper having a lower end spike extension and an upper end tubular neutron shield extension and wherein the pins are retained at their lower ends by a cellular hold down grid (as defined hereinbefore) which is secured to the lower end region of the tubular wrapper, the method comprising the steps of severing the upper and lower end regions of the wrapper to separate the tubular neutron shield and spike extension from the wrapper, severing the wrapper immediately above the cellular hold down grid and withdrawing the combination of hold down grid and bundle of fuel pins from the combination of wrapper and series of bracing grids.
5. A fuel sub-assembly for a liquid metal cooled fast breeder nuclear reactor substantially as hereinbefore described with reference to the accompanying drawings.
6. A method of dismantling a fuel subassembly substantially as hereinbefore described.
Priority Applications (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB20581/78A GB1597189A (en) | 1978-05-18 | 1978-05-18 | Nuclear reactor fuel sub-assemblies |
FR7912611A FR2426311A1 (en) | 1978-05-18 | 1979-05-17 | Fuel sub-assemblage for fast neutron nuclear reactor - has flexible reinforcement grids and lower retaining grid facilitating removal of wrapper for retreatment after irradiation |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB20581/78A GB1597189A (en) | 1978-05-18 | 1978-05-18 | Nuclear reactor fuel sub-assemblies |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1597189A true GB1597189A (en) | 1981-09-03 |
Family
ID=10148282
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB20581/78A Expired GB1597189A (en) | 1978-05-18 | 1978-05-18 | Nuclear reactor fuel sub-assemblies |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB1597189A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4684496A (en) * | 1984-11-16 | 1987-08-04 | Westinghouse Electric Corp. | Debris trap for a pressurized water nuclear reactor |
CN110600144A (en) * | 2019-10-10 | 2019-12-20 | 中国科学院近代物理研究所 | Lower pipe seat buoyancy locking mechanism of lead-based reactor fuel assembly |
-
1978
- 1978-05-18 GB GB20581/78A patent/GB1597189A/en not_active Expired
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4684496A (en) * | 1984-11-16 | 1987-08-04 | Westinghouse Electric Corp. | Debris trap for a pressurized water nuclear reactor |
CN110600144A (en) * | 2019-10-10 | 2019-12-20 | 中国科学院近代物理研究所 | Lower pipe seat buoyancy locking mechanism of lead-based reactor fuel assembly |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed [section 19, patents act 1949] | ||
PCNP | Patent ceased through non-payment of renewal fee |