GB2277828A - Nuclear reactors - Google Patents
Nuclear reactors Download PDFInfo
- Publication number
- GB2277828A GB2277828A GB9309235A GB9309235A GB2277828A GB 2277828 A GB2277828 A GB 2277828A GB 9309235 A GB9309235 A GB 9309235A GB 9309235 A GB9309235 A GB 9309235A GB 2277828 A GB2277828 A GB 2277828A
- Authority
- GB
- United Kingdom
- Prior art keywords
- bore
- sampling
- cylinder
- selector valve
- outlet
- 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.)
- Withdrawn
Links
- 238000005070 sampling Methods 0.000 claims abstract description 38
- 239000000446 fuel Substances 0.000 claims abstract description 23
- 239000012530 fluid Substances 0.000 claims abstract description 9
- 230000008878 coupling Effects 0.000 claims abstract description 8
- 238000010168 coupling process Methods 0.000 claims abstract description 8
- 238000005859 coupling reaction Methods 0.000 claims abstract description 8
- 239000002826 coolant Substances 0.000 claims description 20
- 229910001338 liquidmetal Inorganic materials 0.000 claims description 7
- 230000004992 fission Effects 0.000 claims description 6
- 238000000429 assembly Methods 0.000 description 3
- 238000001514 detection method Methods 0.000 description 3
- 238000012806 monitoring device Methods 0.000 description 3
- 238000007789 sealing Methods 0.000 description 2
- 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 1
- 229910000831 Steel Inorganic materials 0.000 description 1
- 238000011109 contamination Methods 0.000 description 1
- 238000007599 discharging Methods 0.000 description 1
- 230000006698 induction Effects 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 229910052708 sodium Inorganic materials 0.000 description 1
- 239000011734 sodium Substances 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
Classifications
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F16—ENGINEERING ELEMENTS AND UNITS; GENERAL MEASURES FOR PRODUCING AND MAINTAINING EFFECTIVE FUNCTIONING OF MACHINES OR INSTALLATIONS; THERMAL INSULATION IN GENERAL
- F16K—VALVES; TAPS; COCKS; ACTUATING-FLOATS; DEVICES FOR VENTING OR AERATING
- F16K11/00—Multiple-way valves, e.g. mixing valves; Pipe fittings incorporating such valves
- F16K11/02—Multiple-way valves, e.g. mixing valves; Pipe fittings incorporating such valves with all movable sealing faces moving as one unit
- F16K11/06—Multiple-way valves, e.g. mixing valves; Pipe fittings incorporating such valves with all movable sealing faces moving as one unit comprising only sliding valves, i.e. sliding closure elements
- F16K11/078—Multiple-way valves, e.g. mixing valves; Pipe fittings incorporating such valves with all movable sealing faces moving as one unit comprising only sliding valves, i.e. sliding closure elements with pivoted and linearly movable closure members
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N1/00—Sampling; Preparing specimens for investigation
- G01N1/02—Devices for withdrawing samples
- G01N1/10—Devices for withdrawing samples in the liquid or fluent state
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N33/00—Investigating or analysing materials by specific methods not covered by groups G01N1/00 - G01N31/00
- G01N33/0093—Radioactive materials
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
- G21C17/04—Detecting burst slugs
- G21C17/042—Devices for selective sampling, e.g. valves, shutters, rotatable selector valves
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N1/00—Sampling; Preparing specimens for investigation
- G01N1/02—Devices for withdrawing samples
- G01N1/10—Devices for withdrawing samples in the liquid or fluent state
- G01N1/14—Suction devices, e.g. pumps; Ejector devices
- G01N1/1409—Suction devices, e.g. pumps; Ejector devices adapted for sampling molten metals
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N1/00—Sampling; Preparing specimens for investigation
- G01N1/02—Devices for withdrawing samples
- G01N1/10—Devices for withdrawing samples in the liquid or fluent state
- G01N1/16—Devices for withdrawing samples in the liquid or fluent state with provision for intake at several levels
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N1/00—Sampling; Preparing specimens for investigation
- G01N1/02—Devices for withdrawing samples
- G01N1/10—Devices for withdrawing samples in the liquid or fluent state
- G01N1/20—Devices for withdrawing samples in the liquid or fluent state for flowing or falling materials
- G01N1/2035—Devices for withdrawing samples in the liquid or fluent state for flowing or falling materials by deviating part of a fluid stream, e.g. by drawing-off or tapping
- G01N2001/205—Devices for withdrawing samples in the liquid or fluent state for flowing or falling materials by deviating part of a fluid stream, e.g. by drawing-off or tapping using a valve
-
- 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)
- Life Sciences & Earth Sciences (AREA)
- Health & Medical Sciences (AREA)
- General Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Biochemistry (AREA)
- General Physics & Mathematics (AREA)
- Pathology (AREA)
- Analytical Chemistry (AREA)
- Immunology (AREA)
- General Health & Medical Sciences (AREA)
- Plasma & Fusion (AREA)
- Hydrology & Water Resources (AREA)
- High Energy & Nuclear Physics (AREA)
- Mechanical Engineering (AREA)
- Food Science & Technology (AREA)
- Medicinal Chemistry (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Sampling And Sample Adjustment (AREA)
- Multiple-Way Valves (AREA)
Abstract
A fluid sampling device for detecting failed fuel elements in a nuclear reactor comprises a cylinder (27), having a bore (31) parallel to its axis, the cylinder having a plurality of fluid ducts (29) within its wall, each duct having an inlet port in one end face of the cylinder and an outlet port (33 - 43) in the surface of said bore, the outlet ports being located around the bore (31) at least two different distances from said end face; and a selector valve (47) for coupling each outlet port in sequence to a fluid outlet path (63), the selector valve (47) is rotatable within the bore (31), and movable axially of the bore, to align a sampling nozzle (57) with each outlet port (33 - 43), in sequence so that fluid from each outlet port may be sequentially sampled. <IMAGE>
Description
Nuclear Reactors
This invention relates to a fluid sampling device, and to apparatus for detecting failed fuel elements in nuclear reactors which are cooled by liquid metal.
The fuel for nuclear reactors of the fast breeder, liquid metal cooled type is conventionally enclosed in sheaths, a group of such fuel pins being disposed side by side in an open-ended envelope or forming a fuel sub-assembly which, together with a multiplicity of other such sub-assemblies together form the core of the nuclear reactor. Liquid metal such as sodium is caused to flow upwardly through the sub-assembly to remove heat generated by the fuel pins.
It is necessary to be able to detect any failure of the sheathing of a fuel pin of a particular sub-assembly so that that sub-assembly can be removed from the core and replaced, as soon as possible, to avoid contamination of the coolant, and to avoid prejudicing the safety of the reactor.
The detection of failed fuel pins in metal-cooled nuclear reactors of the kind described above has conventionally involved the employment of a coolant sampling pipe for each fuel sub-assembly of the core. The coolant sampling pipes are conventionally terminated at respective ports in the above-core structure, and sequential samples are taken from the coolant sampling pipes by a selector valve comprising a rotary selector which makes sealing contact with each pipe in turn. The coolant samples are fed in turn to a monitoring device which checks for the presence of fission products in the sample, which would indicate one or more fuel sheathing failures in the particular fuel sub-assembly associated with the selected port.
Such conventional coolant sampling arrangements suffer from a disadvantage in that the ports for all of the coolant sampling pipes are located in a single horizontal plane, so that a large area is necessary to accommodate all of the sampling pipes and associated ports, and to enable the selector valve to seal to each port in turn. There may be, for example, 218 pipes and ports.
It is an object of the present invention to provide a sampling device, and apparatus for sampling liquid metal coolant in which the area occupied by the sampling pipes and associated ports in a horizontal plane is reduced.
According to one aspect of the invention there is provided a fluid sampling device comprising a cylinder having a bore parallel to its axis, the cylinder having a plurality of ducts within its wall, each duct having an inlet port in one end face of the cylinder and an outlet port in the surface of said bore, the outlet ports being located around the bore at at least two different distances from said end face; and a selector valve for coupling each outlet port in sequence to a fluid outlet path, said selector valve being rotatable within said bore, and movable axially of the bore, to align a sampling nozzle with each said outlet port in sequence.
According to another aspect of the invention there is provided apparatus for detecting failed fuel elements in a nuclear reactor which is cooled by liquid metal, the apparatus comprising a plurality of sampling tubes each for sampling coolant which has passed through a respective fuel or breeder sub-assembly; a cylinder having a bore parallel to its axis, and having a plurality of ducts within its wall, each duct having an inlet port at one end face of the cylinder and an outlet port in the surface of said bore, the outlet ports being located around the bore at at least two different distances from said end face; means coupling each sampling tube to a respective one of said said inlet ports; a selector valve for coupling each outlet port in sequence to a coolant sample outlet path, said selector valve being rotatable within said bore, and movable axially of the bore, to align a sampling nozzle with each said outlet port in sequence; and means coupled to said coolant sample outlet path to check the level of fission products in said path.
An embodiment of the invention will now be described, by way of example, with reference to the accompanying drawings, in which
Figure 1 is a schematic plan view of a core of a liquid metal cooled nuclear reactor,
Figure 2 is a schematic vertical cross-sectional view of a coolant sampling apparatus in accordance with the invention, taken on a line II-II of Figure 4,
Figure 3 is a horizontal cross section taken on a line
III-III of Figure 2,
Figure 4 is a horizontal cross-sectional view taken on a line IV-IV of Figure 2, and
Figure 5 is a schematic vertical sectional view of part of the above-core structure of a nuclear reactor including the present invention.
Referring to Figure 1 of the drawings, the core 1 of a metal-cooled fast nuclear reactor comprises a structure of fuel sub-assemblies 3. Two failed-fuel detection and location (FFDL) units 5,7 incorporating the present invention are located above the core structure, each unit serving a respective half of the fuel sub-assemblies.
Referring to Figures 2,3 and 4, each FFDL unit 5,7 comprises a lower cylinder 9 having an annular flange 11 at its upper end. The flange 11 has five rings of apertures 13 therethrough (only three of which appear in the particular cross section of Figure 2). Each aperture 11 receives a respective ferrule 15 which is welded to the top of a respective sampling tube 17. Each sampling tube extends downwards and outwards to terminate immediately above the top of its respective fuel sub-assembly 3 of
Figure 1. During assembly, each ferrule 15 is pushed upwards through the aperture 13, and a circlip or a split collar 19 is positioned in a groove 21 in the ferrule wall. The ferrule is then lowered so that the circlip or split collar sits in a groove 23 in the upper surface of the flange 11, thereby retaining the ferrule 15 axially in the aperture 13. A perforated annular retaining plate 25 is then lowered over the ferrules.
An annular cylinder 27 has rings of bores 29 therein, forming coolant sample ducts. The bores are counterbored at their lower ends to receive the tips of the ferrules 15. The cylinder 27 is lowered over the ferrules 15 to sit on the plate 25, with each ferrule located in a respective counterbore and forming a liquid-tight connection with the respective bore 29. The cylinder is bolted to the flange 11. The bores 29 extend vertically part of the way up the height of the cylinder 27 and are then inclined towards the axis of the cylinder so that they terminate as ports communicating with the bore 31 of the cylinder 27. Bores 29 in the outer rings terminate higher up the bore 31 of the cylinder 27 than those in the inner rings, so that in the embodiment shown there are six different levels of ports, such as ports 33-43, up the height of the bore 31. These six levels are also illustrated in Figure 2(a).
A selector valve 45 is located in the bore 31. The valve 45 comprises a vertical shaft 47 having at its lower end three radially projecting lugs 49,51,53 spaced at 120e round the shaft.
It should be notS hat the section line II-II in Figure 4 is not straight, but is angled to pass through the lugs 49 and 53. Those two lugs therefore appear in Figure 2 to be diametrally opposite, but this is merely for ease of illustration. The lug 49 contains a selector block 55 made of hard-faced steel, which bears against the wall of the bore 31. The block has a vertically-extending recess 57 in its vertical outer face 59. The recess 57 has a tapered portion 61 which communicates with a bore 63 in the lug 49 and extending through the shaft 47. The bore 63 is coupled to a device 65 which monitors the presence of fission products in the coolant samples, as will be described later. Each of the lugs 51 and 53 houses a spring-loaded plunger 67,69, respectively. The plungers bear against the cylinder wall around the bore 31, thereby together urging the selector block 55 into sealing contact with the cylinder wall. The whole of the selector apparatus is enclosed within a vertical cylinder 71, which is sealed to the flange 11.
Referring also to Figure 5, the shaft 47 is rigidly attached to the lower end of the housing of a helical annular linear induction pump (HALIP)73 which pumps the sample from the bore 63 in the shaft 47 up to the fission product monitor 65. Operation of the selector valve is effected by an electric stepper motor 75 which rotates the pump housing 73, and hence the shaft 47, through increments of angle corresponding to the spacing of the ports 33-43, etc. round the bore 31, and by hydraulic or other jacking apparatus 77, which can raise and lower the shaft 47 to set the selector block 55 at the required one of three levels. It will be seen from Figure 2(a) that at each of its height settings the selector block can connect to two different levels of outlet ports.
In operation of the failed fuel detection and location (FFDL) apparatus, the selector valve is set at its lowest position by the jacking apparatus 77 and is rotated stepwise from each position to the next by the motor 75. The valve is then raised by the apparatus 77 and the rotation is repeated. The raising and rotation are again repeated, so that each sampling tube 17 is connected in turn to the bore 63 and thence to the monitoring device 65. The device 65 gives a warning if any sample contains more than a predetermined level of fission products, and the position of the selector valve at that instant indicates which sample tube is being monitored, and therefore which sub-assembly contains the failed fuel pin.
It will be seen that while the selector block 55 is aligned with one port, the other outlet ports will be discharging into the bore 31, so that the bore 31 contains the samples from all of the other sampling tubes. This material flows downwards through the spaces between the lugs 49,51,53 and into the bore 79 of the cylinder 9 and thence back to the coolant pool (not shown). One of the sampling tubes, reference 81, is not associated with a fuel sub-assembly, but turns upwards into the path of the coolant flowing down through the bore 79. It therefore produces a bulk sample, which is fed to the monitoring device 65, in its turn, via the port 33. The selector valve 45 is shown in Figure 2 in position for receiving that bulk sample.
Although a particular arrangement of bores in the cylinder 27 is shown in Figure 3 wherein there are five rings of bores each comprising 38 bores and one ring comprising 28 bores, any required number of bores may be provided. Similarly there may be more or fewer than six levels of ports in the wall around the bore 31, provided that there are at least two levels.
It will be seen that by the provision of the cylinder 27 having ports at various levels up the height of its bore 31, and the selector valve which can both rotate and move between the levels, a more compact sampling arrangement is provided.
Claims (11)
1. A fluid sampling device comprising a cylinder having a bore parallel to its axis, the cylinder having a plurality of ducts within its wall, each duct having an inlet port in one end face of the cylinder and an outlet port in the surface of said bore, the outlet ports being located around the bore at at least two different distances from said end face; and a selector valve for coupling each outlet port in sequence to a fluid outlet path, said selector valve being rotatable within said bore, and movable axially of the bore, to align a sampling nozzle with each said outlet port in sequence.
2. Apparatus for detecting failed fuel elements in a nuclear reactor which is cooled by liquid metal, the apparatus comprising a plurality of sampling tubes each for sampling coolant which has passed through a respective fuel or breeder sub-assembly; a cylinder having a bore parallel to its axis, and having a plurality of ducts within its wall, each duct having an inlet port at one end face of the cylinder and an outlet port in the surface of said bore, the outlet ports being located around the bore at at least two different distances from said end face; means coupling each sampling tube to a respective one of said said inlet ports; a selector valve for coupling each outlet port in sequence to a coolant sample outlet path, said selector valve being rotatable within said bore, and movable axially of the bore, to align a sampling nozzle with each said outlet port in sequence; and means coupled to said coolant sample outlet path to check the level of fission products in said path.
3. Apparatus as claimed in Claim 2, wherein the selector valve comprises a shaft having a lug projecting radially therefrom, said lug carrying the sampling nozzle.
4. Apparatus as claimed in Claim 3, comprising two additional lugs projecting from the shaft, the additional lugs carrying spring-loaded plungers which bear against the surface of the bore to urge the sampling nozzle into contact with said surface.
5. Apparatus as claimed in any one of Claims 2-4, wherein the outlet ports except when aligned with the sampling nozzle all discharge into said bore; and wherein an additional sampling tube and a corresponding duct in the cylinder are provided for sampling the coolant in the bore.
6. Apparatus as claimed in any one of Claims 2-5, wherein each inlet port comprises a counterbored end portion of the respective duct; and wherein the means coupling the sampling tubes to the inlet ports comprises a respective ferrule at the end of each sampling tube, the ferrule having a tip which is housed in the counterbored region of the respective duct.
7. Apparatus as claimed in any preceding claim, comprising stepping motor means for rotating the selector valve within the bore.
8. Apparatus as claimed in any preceding claim, comprising jacking means for moving the selector valve axially of the bore.
9. Apparatus as claimed in Claim 8, wherein the jacking means is hydraulically actuated.
10. Apparatus for detecting failed fuel elements, substantially as hereinbefore described with reference to the accompanying drawings.
11. A nuclear reactor including apparatus as claimed in any preceding claim.
Priority Applications (3)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB9309235A GB2277828A (en) | 1993-05-05 | 1993-05-05 | Nuclear reactors |
| JP10431394A JP3561949B2 (en) | 1993-05-05 | 1994-04-20 | Damaged fuel detector |
| JP2004049742A JP3878611B2 (en) | 1993-05-05 | 2004-02-25 | Damaged fuel detection device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB9309235A GB2277828A (en) | 1993-05-05 | 1993-05-05 | Nuclear reactors |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| GB9309235D0 GB9309235D0 (en) | 1993-06-16 |
| GB2277828A true GB2277828A (en) | 1994-11-09 |
Family
ID=10734955
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB9309235A Withdrawn GB2277828A (en) | 1993-05-05 | 1993-05-05 | Nuclear reactors |
Country Status (2)
| Country | Link |
|---|---|
| JP (2) | JP3561949B2 (en) |
| GB (1) | GB2277828A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP2101092A1 (en) * | 2008-03-11 | 2009-09-16 | Qiagen GmbH | Fluid control device for microfluidic systems |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4207922A (en) * | 1976-12-09 | 1980-06-17 | Commissariat A L'energie Atomique | Liquid sampling apparatus |
| US4332639A (en) * | 1979-02-21 | 1982-06-01 | Electric Power Research Institute, Inc. | Failed element detection and location system and method for use in a nuclear reactor |
| EP0073723A1 (en) * | 1981-08-31 | 1983-03-09 | Novatome | Device for detecting ruptures in the cladding of fuel assemblies of a fast breeder reactor |
-
1993
- 1993-05-05 GB GB9309235A patent/GB2277828A/en not_active Withdrawn
-
1994
- 1994-04-20 JP JP10431394A patent/JP3561949B2/en not_active Expired - Fee Related
-
2004
- 2004-02-25 JP JP2004049742A patent/JP3878611B2/en not_active Expired - Fee Related
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4207922A (en) * | 1976-12-09 | 1980-06-17 | Commissariat A L'energie Atomique | Liquid sampling apparatus |
| US4332639A (en) * | 1979-02-21 | 1982-06-01 | Electric Power Research Institute, Inc. | Failed element detection and location system and method for use in a nuclear reactor |
| EP0073723A1 (en) * | 1981-08-31 | 1983-03-09 | Novatome | Device for detecting ruptures in the cladding of fuel assemblies of a fast breeder reactor |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP2101092A1 (en) * | 2008-03-11 | 2009-09-16 | Qiagen GmbH | Fluid control device for microfluidic systems |
Also Published As
| Publication number | Publication date |
|---|---|
| GB9309235D0 (en) | 1993-06-16 |
| JP2004198440A (en) | 2004-07-15 |
| JPH06331786A (en) | 1994-12-02 |
| JP3878611B2 (en) | 2007-02-07 |
| JP3561949B2 (en) | 2004-09-08 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| WAP | Application withdrawn, taken to be withdrawn or refused ** after publication under section 16(1) |