GB2179195A - Nuclear reactor control rod support - Google Patents

Nuclear reactor control rod support Download PDF

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Publication number
GB2179195A
GB2179195A GB08617203A GB8617203A GB2179195A GB 2179195 A GB2179195 A GB 2179195A GB 08617203 A GB08617203 A GB 08617203A GB 8617203 A GB8617203 A GB 8617203A GB 2179195 A GB2179195 A GB 2179195A
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United Kingdom
Prior art keywords
rod
rods
control
rotation
control rods
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Granted
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GB08617203A
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GB2179195B (en
GB8617203D0 (en
Inventor
Susumu Nakazato
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CBS Corp
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Westinghouse Electric Corp
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Publication of GB8617203D0 publication Critical patent/GB8617203D0/en
Publication of GB2179195A publication Critical patent/GB2179195A/en
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Publication of GB2179195B publication Critical patent/GB2179195B/en
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/06Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
    • G21C7/10Construction of control elements
    • G21C7/117Clusters of control rods; Spider construction
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

In a nuclear reactor control rod support arrangement wherein the control rods are movable in their longitudinal direction between a first end position in which the control rods are fully inserted into the core and a second end position in which the control rods are retracted from the core, and wherein guide elements contact regions of the outer surface of each control rod whereby the control rods are subject to wear, there is provided a displacement device operatingly coupled to the control rods for periodically rotating the control rods in order to change the locations on the outer surfaces of the control rods at which the control rods are contacted by the guide elements. Embodiments are described in which the control rods are connected to a spider by means which causes rod rotation each time the rods are brought to their second end position.

Description

SPECIFICATION Nuclear reactor control rod support Known nuclear reactors, such as pressurized water reactors, include control rods that contain neutron absorbers with varying absorption capability for shutdown or power level control and sometimes also non-neutron absorbing materials to first breed plutonium and to later burn it as a fuel component.
Generally, these rods are mounted, via their upper end,to an assembly, or spider, which supports a plurality of such rods from simultaneous movement into and out of the reactor active core region. While in the core region,thecontrolrodsenterfuel assembly thimbles.
The assembly of a spider and a plurality of control rods may be designated a rod cluster control or a water displacer rod assembly, depending on the function to be performed bythe control rods.
During reactor operation, the control rods are withdrawn from the active core region by lifting the assembly into the upper internals of the reactor pressure vessel. Movements of the assembly are guided by a guidetube presenting a plurality of guide sections, or cards, which contactthe rods in respective regions. The number of guide sections provided for each control rod is selected as a compromise between the desire to reduce drag forces, which entails a minimum number guide sections, and the need to reduce the distance between guide sections in order to limit the amplitude offlow-inducedvibration forces.
Drag forces can be controlled by design approaches which limit the drag forces, and thus reduce drag friction, bya hydraulic pressure balance.
The drag which does exist is a source ofwearalong each rod surface which slides along a guide section. In addition, when the rods are being maintained in their raised position in the guide tube, they experience movement relative to the guide sections due to flow induced vibration, which movement is a further cause for wear.
Such wear can influence the useful life ofthe control rods.
The rate of such wear is partly determined by the materials ofthecontrol rods and guide sections. The latter are usually made of stainless steel, while neutron absorber control rods are generally sheathed in stainless steeland water displacer rods are sheathed in a non-neutron absorbing material such as zircalloy.
Thus, wear imposed on neutron absorbing rods occurs primarily during insertion and withdrawal movements. In the case ofwater displacer rods, movements are limited, butsincethe material is softer, these rods are more susceptible to wear due to flow inducedvibrationwhilethe rods arse in their raised, or parked, position.
Once the outer wall of a control rod has been worn to a certain depth at one location,the rod must be replaced. Therefore, if such wear can be retarded, the useful life ofthe spider-rod assembly can be increased.
It is the principal object of the invention to provide a nuclear reactor control rod drive with drive shaft arrangements which will substantially increase wear resistance and, as a result operating life of the drive shafts.
With this object in view, the present invention resides in a nuclear reactor including a core, having a plurality of control rods disposed therein movable in their longitudinal direction between a first end position in which the control rods (4) are fully inserted into the core and a second end position in which the control rods (4) are retracted from the core, and guide means in contract with discrete regions ofthe outer surface of each control rod at least when the control rods are in the vicinity of the second end position, the control rods being subject to wear as a result of sliding contact with the guide means, characterized by displacement means (36-62) operatively coupled to said control rods (4) for periodically rotating said control rods (4) in orderto change the locations on the outer surfaces of said control rods at which said control rods (4) are contacted by said guide means (88).
The invention will become more readily apparent from the following description of a preferred embodi ment thereof shown, by way of example only, in the accompanying drawings, wherein: Figure 1 is an elevational view, partly in crosssection, of a rod and spider assembly incorporating one preferred embodiment of a rod displacement arrangement according to the invention.
Figure 2 isa cross-sectional detail view of a portion of the embodiment of Figure 1.
Figure 3 is a developed, detail view of a camming structure employed inthe embodiment of Figure 2.
Figure 4 is a view similarto that of Figure 2 illustrating a second embodiment of the invention.
Figure 5 is a cross-section detail view illustrating a third embodiment of the invention.
Figure 6 is a detail ptan view illustrating one type of guide structure with which an arrangement according to the invention can be employed.
figure 7 is aview similar to that of Figure 6 illustrating a second type of guide structure.
AsshowninFigurei a rodandspiderassembly includesa spider 2 which supports a plurality of rods 4 for vertical movement as needed to achieve the required reactor control. Each rod is supported on spider 2 via a respective support unit 6, one embodi ment of which is shown in Figure 2.
The support unit 6 is composed of a housing 8 and a housing cap 1 Owhich together delimit a cylindrical chamber 12. Each control rod 4 is connected to an extension piece 16 into which is threaded a support rod 20 that extends veritically through unit 6 and its chamber 12and is movable axially relative to unit 6.
A ring 22 is fixed to rod 20 and a compression spring 24 is interposed between ring 22 and the bottom wall ofchamber 12. Thus, rod 20 is supported by unit6 via spring 24.
Reverting to Figure 1, when the assembly composed of spider 2 and rods 4 is raised into the upper internals of the reactor vessel in orderto withdraw rods 4from the active core region of the reactor, each rod 4 is guided by guide sections or cards 30 (note: this reference numeral must be added to Figure 1), which are spaced apart around the associated rod 4.
Contact between each rod 4 and its associated guide sections or cards 30 produces drag forces whenever rods 4are raised or lowered. These drag forces, of course, produce a certain amount ofwear on the outer surface ofthe rod 4.
Asthe assembly 2,4 arrives at its uppermost position, the upper end of each support rod 20 comes to abut against a stop 34 installed in the guide tube and positioned so that when assembly 2,4 is in its uppermost position, each ring 22 will have been pushed downwardly in chamber 12fromthe position illustrated in Figure 2 and spring 24 will be essentially fully compressed.
According to the present invention, this downward movement of ring 22, together with support rod 20, extension piece 16 and the associated rod 4 will be accompanied by a rotation relative to housing 8. This rotation will change the locations of each rod4 which are in contact with itsassociatedguide sections or cards.
One suitable mechanism for effecting the desired rotation is illustrated in developed form in Figure 3.
This mechanism includes a boss 36 on the outer surface of support rod 20, swell as a group of upper bosses 38,40,42... and a group of tower bosses 44, 46... provided on the wall ofchamber 12 and extending aroundthe periphery thereof. Boss 36 is provided with a lower camming surface 50 arranged to cooperate with guide surfaces 52,54 on lower bosses 44,46, respectively. In addition, boss 36 is provided with anuppercamming surface58arranged to cooperate with guide surfaces such as 60,62 on upper bosses 40,42,. respectively.
Rotation of support rod 20, together with extension piece 16 and the associated control rod iseffected eachtimethe assembly 2,4 is raised into the parked position and then lowered again into the reactor core.
When the assembly reaches its uppermost position, the upperend of each support rod 20 its halted by its associated stop member 34. Spider2 and housings8 then continue to move upwardly over a short distance relative to support rods 20so that camming surface 50 of cam 36 slides along guide surface 52, thereby effecting an incremental rotation of support rod 20.
Thus, cam 36 comes into alignment with the gap between lower bosses 44 and 46.
Then, when spider 2 is again lowered, each support rod20 initially remains in contact with its associated stop34sothat each housing 8 moves downwardly relative to its associated rod 20 as spring 24 expands.
During thistime, camming surface 58 will slide upwardly along guide surface 60 of upper boss 4Q, thereby effecting a further incremental rotation of support rod 20 and bringing boss 36 into alignment with the gap between upper bosses 40 and 42.
According to one embodiment ofthe invention, the total rotation imparted to rod 20 by the sliding movement along surfaces 52 and 60 will be of the orderof45 degrees. Then whenthe assembly is lowered into the reactor core, each control rod4will have an angular position which is offset by 45 degrees from the previous position. As a result, each guide section, or card will contact a new surface area of its associated rod 4, at a location which is angularly offset from the surface area which it previously contacted.
Figure 4 illustrates an alternative rod support unit 64 which includes a top end plug 66 fastened to spider2 and having an axial passage for support rod 20. A housing 68 is screwed onto the bottom of plug 66 and is then secured thereto bya locking pin. This embodiment allows for a larger space within housing 68 to accommodate a larger spring 24 and facilitate formation of bosses, such as 38,40, etc of Figure 3, on the inner wall of housing 68.
Figure 5 illustrates a second embodiment ofa mechanism for rotating each rod in accordance with the present invention This embodiment includes a housing 68 having the sameform as that shown in Figure 4. However, one advantage of the structure iliustrated in Figure is that the interior of housing 68 need not be provided with bosses, such as 38,... Inthis embodiment the control or water displacer rod is supported by means ofasupport rod 70 which, in turn, is supported in housing 68 by means of compression spring 24. Extending downwardly into housing 68 is a drive rod 72 which extends upwardlythrough the top end plug connected to rod 68, thetop end plug being as shown in Figure 4and not being illustrated in Figure 5.The upper end of drive rod 72 is disposed to engage the stop 34shown in Figure 1. The lower end of drive rod 72 carries a rotation producing member 74 provided with two individual, angularly offset external threads 75 which engage in helical recesses 76 in the innerwall of housing 6S.The The lower end of member74 has an annularsawtooth structure composed of verticaLsurfaces alternating with gradually sloping surface.
Fixed to the upper end of support 70 isa disk78 having, at its top, a sawtooth structure constructedto mate with the sawtooth structure at the lower end of member 74. The lower end of disc 78 is equally provided with arr annular sawtooth structure composed of vertical surfaces alternating with inclined surfaces, with these inclined surfaces being inclined in the opposite direction to the gradually sloping surfaces at the upper end of disk 78.
In the normal operating state, when spider 2 is spaced from the retracted position, spring 24 is in its elongated state and presses disk78against member 74, so that member 74 and drive rod 72 are equally supported by spring 24. The spider is lifted into its retracted position, and the upper end of drive rod 72 comes to abut against stop 34, continued upward movement of housing 68togetherwith spider2 causes the external threads 75 to be guided in helical recesses 76, thereby imposing a rotational movement on member 74, so that member74 is thereby driven downwardly relative to housing 68.
As a result of cooperation of the sawtooth structures atthe lower end of member 74 andthe upper end of disk 78, this equally causes disk 78, rod 70 and the control rod supported thereby to rotate and to move downwardly relative to housing 68. This rotational movement is not impeded by spring 24 since, as is apparent from Figure 5, the upper end of spring 24 will slide along the inclined surfaces atthe lower end of disk 78. The lower end of spring 24 is seated in a bore formed atthe bottom ofthe chamber defined by housing 68, so that spring 24 is itself prevented from rotating However, spring 24 will be axially depressed by the downward movement of disk 78 relative to housing 68.
According to one exemplary embodiment of the invention, drive rod 72, threads 75 and recesses 76 are dimensioned to cause the rod rotation system to undergo a rotation of between 90 and 180 degrees as the spider moves to its fully retracted position.
Then, as the spider is subsequently moved downwardly away from the retracted position, spring 24 becomes active to urge disk 78 upwardly relative to housing 68. This produces an upward force on member74which causes member74to move upwardly relative to housing 68 while threads 75 travel along recesses 76 in order to also rotate member 74. However, during this movement, the upper end of spring 24 will come to abut against one of the vertical surfaces of the sawtooth structure at the lower end of disk 78, whereupon further rotation of disk 78 and support rod 70 will be prevented and the sloping surfaces ofthe sawtooth structure at the lower end of member74will be forced to slide along the sloping surfaces atthe upper end of disk 78.Atthe end ofthis return movement, member 74 and disk 78 will again be in the positions shown in Figure 5, but disk 78, support rod 70 and the control rod supported thereby will have undergone a net rotation of 90 .
While Figure 5 illustrates sawtooth structures, each composed of 4teeth, it will be appreciatedthat a different numberofteeth can be provided, if desired, and the inclination of threads 75 and helical recesses 76 can be varied in orderto produce a different amount of rotation during each retraction movement of the spider.
It will be noted that in the normal operating position shown in Figure 5, whenthe spider assembly is spaced from its retracted position, each vertical surface of the sawtooth at the bottomof member74 is spaced circumferential ly from the associated verticaL surface of the sawtooth structure at the top of disk 78.
This spacing is provided to assure that, when member 74 is being urged upwardly relative to housing 68by the action of spring 24, member 74 will cometo rest at a positionwherethe vertical surfaces of its associated sawtooth structure will be properly positioned relative to the vertical surfacesofthe sawtooth structure at the top of disk 78 to produce the next90" rotation of disk 78 and the components secured thereto.
A significant advantage of this structure is that very little machining must be carried at the interior of housing 68. In effect, the only machining required is theformation ofasmalldiameterboreatthebottom ofthe chamber enclosed by housing 68 and the machining of helicai grooves 76 nearthe open top of housing 68. The machining of such grooves atthat location is a relatively simple matter.
Figures 6 and 7 are detail plan views illustrating portions of two types of guide arrangementswhich can be employed for guiding rods 4 primarily during movement in the upper internals of the reactor pressure vessel. Such guide arrangements are fixed in the pressure vessel so-that the rods move vertically therepast.
Figure 6 illustrates a portion of one guide card which can be employed for guiding the rods of rod cluster control. A complete card can be in the form of a cruciform structure, one arm ofwhich is illustrated.
This card is compared simply of a plate 82 having a central slot 84 for passage of an arm of spider 2, and accurate openings 86. Each opening 86 guides a respective rod, so that the total number of openings 86 is a card 82 will equal the number of rods carried by spider 2 of Figure 1. Plate 82 is of a suitable metal and of a suitable thickness, for example 3.7 cm.
The openings 86 are slightly larger in diameterthan the rods 4which they guide so that, as a general rule, each rod 4 bears against a particularpartofthe periphery of its associated opening 86, at which location the rod 4 will be subject to wear. When rod 4 is rotated, the portion of its surface which bears against the particular part of opening 86 changes.
Typically, a number of, e.g. five, cards orplates, 82 is provided, the cards being spaced apart vertically along the upper portion ofthe pressure vessel interior.
Figure 7 illustrates a similar portion of a guide arrangement suitabiefor guiding the rods of a water displacer rod assembly. Here, the guide region is delineated by upper and lower end plates 88 having slots 90 and between which extend, vertically, a plurality of C-tubes, such as 92, and a plurality of half-tube assemblies, such as 94. Each tube 92 and assembly 94 guides a respective water displacer rod.
As shown, each assembly 94 is composed of two tube sections each coextensive with less than half the diameter of an associated rod.
Here, again, the internal diameter of tubes 92 and assemblies 94 are slightly less than the diameters of rods 4so that each rod will tend to bear against a particular partof its associated tube or haStube assembly.
In the case of water displacement rods, the abovedescribed rotation will have the effect of renewingthe locations at which the guide sections or cards bear against the rod-surfaces, so that the locations where wear occurs will be varied. The new contact surfaces on each rod 20 will previously have become oxidized to form a hard zirconium layerwhich serves to retard wear.
The magnitude of each rotation step, for example 45 degrees, can be selected to take advantage of the longitudinal growth of zircalloy due to fast fluence effects while the rods are in the reactor core. As a result, evenafterthe rods have undergone a rotation of 360 degrees, the new wear locations will not coincide with the locations which existed prior to the full 360 degrees of rotation. Moreover, the resulting helical wear paths will have a less significant effect on the longitudinal strength of the control rods.
In the case of rod cluster control, the magnitude of each rotation step can beselectedto renew the contactsurfaces, and also to keep the wear lines symetrically located. This will reduce any effect which the wear lines may have upon bowing of the control rods.
It will be understoodthatthe above description of the present invention is susceptible to various mod lfications, changesand adaptations, andthesameare intended to be comprehended within the meaning and range of equivalents of the appended claims.
CtAIMS A control rod support arrangement for a nuclear
**WARNING** end of DESC field may overlap start of CLMS **.

Claims (6)

  1. **WARNING** start of CLMS field may overlap end of DESC **.
    by the downward movement of disk 78 relative to housing 68.
    According to one exemplary embodiment of the invention, drive rod 72, threads 75 and recesses 76 are dimensioned to cause the rod rotation system to undergo a rotation of between 90 and 180 degrees as the spider moves to its fully retracted position.
    Then, as the spider is subsequently moved downwardly away from the retracted position, spring 24 becomes active to urge disk 78 upwardly relative to housing 68. This produces an upward force on member74which causes member74to move upwardly relative to housing 68 while threads 75 travel along recesses 76 in order to also rotate member 74. However, during this movement, the upper end of spring 24 will come to abut against one of the vertical surfaces of the sawtooth structure at the lower end of disk 78, whereupon further rotation of disk 78 and support rod 70 will be prevented and the sloping surfaces ofthe sawtooth structure at the lower end of member74will be forced to slide along the sloping surfaces atthe upper end of disk 78.Atthe end ofthis return movement, member 74 and disk 78 will again be in the positions shown in Figure 5, but disk 78, support rod 70 and the control rod supported thereby will have undergone a net rotation of 90 .
    While Figure 5 illustrates sawtooth structures, each composed of 4teeth, it will be appreciatedthat a different numberofteeth can be provided, if desired, and the inclination of threads 75 and helical recesses 76 can be varied in orderto produce a different amount of rotation during each retraction movement of the spider.
    It will be noted that in the normal operating position shown in Figure 5, whenthe spider assembly is spaced from its retracted position, each vertical surface of the sawtooth at the bottomof member74 is spaced circumferential ly from the associated verticaL surface of the sawtooth structure at the top of disk 78.
    This spacing is provided to assure that, when member 74 is being urged upwardly relative to housing 68by the action of spring 24, member 74 will cometo rest at a positionwherethe vertical surfaces of its associated sawtooth structure will be properly positioned relative to the vertical surfacesofthe sawtooth structure at the top of disk 78 to produce the next90" rotation of disk 78 and the components secured thereto.
    A significant advantage of this structure is that very little machining must be carried at the interior of housing 68. In effect, the only machining required is theformation ofasmalldiameterboreatthebottom ofthe chamber enclosed by housing 68 and the machining of helicai grooves 76 nearthe open top of housing 68. The machining of such grooves atthat location is a relatively simple matter.
    Figures 6 and 7 are detail plan views illustrating portions of two types of guide arrangementswhich can be employed for guiding rods 4 primarily during movement in the upper internals of the reactor pressure vessel. Such guide arrangements are fixed in the pressure vessel so-that the rods move vertically therepast.
    Figure 6 illustrates a portion of one guide card which can be employed for guiding the rods of rod cluster control. A complete card can be in the form of a cruciform structure, one arm ofwhich is illustrated.
    This card is compared simply of a plate 82 having a central slot 84 for passage of an arm of spider 2, and accurate openings 86. Each opening 86 guides a respective rod, so that the total number of openings 86 is a card 82 will equal the number of rods carried by spider 2 of Figure 1. Plate 82 is of a suitable metal and of a suitable thickness, for example 3.7 cm.
    The openings 86 are slightly larger in diameterthan the rods 4which they guide so that, as a general rule, each rod 4 bears against a particularpartofthe periphery of its associated opening 86, at which location the rod 4 will be subject to wear. When rod 4 is rotated, the portion of its surface which bears against the particular part of opening 86 changes.
    Typically, a number of, e.g. five, cards orplates, 82 is provided, the cards being spaced apart vertically along the upper portion ofthe pressure vessel interior.
    Figure 7 illustrates a similar portion of a guide arrangement suitabiefor guiding the rods of a water displacer rod assembly. Here, the guide region is delineated by upper and lower end plates 88 having slots 90 and between which extend, vertically, a plurality of C-tubes, such as 92, and a plurality of half-tube assemblies, such as 94. Each tube 92 and assembly 94 guides a respective water displacer rod.
    As shown, each assembly 94 is composed of two tube sections each coextensive with less than half the diameter of an associated rod.
    Here, again, the internal diameter of tubes 92 and assemblies 94 are slightly less than the diameters of rods 4so that each rod will tend to bear against a particular partof its associated tube or haStube assembly.
    In the case of water displacement rods, the abovedescribed rotation will have the effect of renewingthe locations at which the guide sections or cards bear against the rod-surfaces, so that the locations where wear occurs will be varied. The new contact surfaces on each rod 20 will previously have become oxidized to form a hard zirconium layerwhich serves to retard wear.
    The magnitude of each rotation step, for example 45 degrees, can be selected to take advantage of the longitudinal growth of zircalloy due to fast fluence effects while the rods are in the reactor core. As a result, evenafterthe rods have undergone a rotation of 360 degrees, the new wear locations will not coincide with the locations which existed prior to the full 360 degrees of rotation. Moreover, the resulting helical wear paths will have a less significant effect on the longitudinal strength of the control rods.
    In the case of rod cluster control, the magnitude of each rotation step can beselectedto renew the contactsurfaces, and also to keep the wear lines symetrically located. This will reduce any effect which the wear lines may have upon bowing of the control rods.
    It will be understoodthatthe above description of the present invention is susceptible to various mod lfications, changesand adaptations, andthesameare intended to be comprehended within the meaning and range of equivalents of the appended claims.
    CtAIMS A control rod support arrangement for a nuclear
    reactor including acre, having a plurality of control rods disposed therein movable in their longitudinal direction between a first end position in which the control rods (4) are fully inserted into the core and a second end position in which the control rods (4) are retracted from the core, and guide means in contract with discrete regions of the outer surface of each control rod at least when the control rods are in the vicinity ofthe second end position, the control rods being subjectto wear as a result of sliding contract with the guide means, characterized by displacement means (36-62) operatively coupled to said control rods (4) for periodically rotating said control rods (4) in orderto change the locations on the outer surfaces of said control rods at which said control rods (4) are contacted by said guide means (88).
  2. 2. An arrangement as claimed in claim 1 characte- rized in that said control rods are associated with said support means to enable said control rodsto undergo a limited movement relative to said support means, in the longitudinal direction of said control rods, when said control rods are broughtto the second end position, and said displacement means effect rotation of said control rods in response to such limited movement.
  3. 3. An arrangement as claimed in claim 2, characterized in that said displacement means comprise a camming mechanism coupling each said control rods to said support meansfor effecting the periodic rotation of each said control rod, whereby the periodic rotation is relative to said support means.
  4. 4. An arrangement as claimed in claim 3, characte rized that for each said control rod, said displacement means comprise a first member structurally separate from said control rod and mounted in said supportmeanstoundergo rotation and vertical movement relative to said support means when said control rod is brought to the second end position, and a drive member carried by said support rod and arranged to undergo rotation, in responseto rotation of said first member, in a first direction during movement ofthe control rod to the second end position.
  5. 5. An arrangement as claimed in claim 4, characterized inthatforeach said control rod, said displace- ment means further comprise a compression spring interposed between said control rod and said support meansfor urging said control rod upwardly relative to said support means while permitting movement of said rod relative to said support means in the longitudinal direction of said rod when said rod is in the vicinity of said second end position.
  6. 6. An arrangement as claim in claim 5, characte- rized in that said spring (24) is operatively associated with said drive memberfor blocking rotation of said drive member inthe direction opposite to saidfirst direction.
GB08617203A 1985-08-08 1986-07-15 Nuclear reactor control rod support Expired GB2179195B (en)

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US76372285A 1985-08-08 1985-08-08

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GB2179195A true GB2179195A (en) 1987-02-25
GB2179195B GB2179195B (en) 1989-01-18

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FR (1) FR2586131B1 (en)
GB (1) GB2179195B (en)
IT (1) IT1198008B (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0313365A2 (en) * 1987-10-21 1989-04-26 Westinghouse Electric Corporation Control rod support having planar wear surfaces
US5889832A (en) * 1995-12-26 1999-03-30 Framatome Nuclear reactor control cluster having removable rods

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* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2657810B2 (en) * 1988-01-11 1997-09-30 フラマトメ Stainless steel tubular elements with improved wear resistance
CN112670000B (en) * 2020-12-11 2024-03-22 中广核研究院有限公司 Flexible control rod assembly and star frame thereof

Citations (1)

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Publication number Priority date Publication date Assignee Title
GB1491552A (en) * 1974-02-26 1977-11-09 Kraftwerk Union Ag Nuclear reactor

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US3137276A (en) * 1955-08-30 1964-06-16 Kahn David Inc Protract-retract mechanism and writing instrument including same
FR1217059A (en) * 1958-11-18 1960-05-02 Commissariat Energie Atomique New automatic handling clamp
GB961246A (en) * 1962-06-07 1964-06-17 Theodore Francis Henry Barrey Writing instruments
FR1512350A (en) * 1966-05-12 1968-02-09 Commissariat Energie Atomique Gripper
FR2501892B1 (en) * 1981-03-13 1985-10-25 Framatome Sa NUCLEAR REACTOR WITH DEVICE FOR GUIDING THE CONTROL CLUSTERS
FR2547100B1 (en) * 1983-06-03 1985-08-30 Framatome Sa GUIDANCE DEVICE FOR NUCLEAR REACTOR CONTROL CLUSTERS

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1491552A (en) * 1974-02-26 1977-11-09 Kraftwerk Union Ag Nuclear reactor

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0313365A2 (en) * 1987-10-21 1989-04-26 Westinghouse Electric Corporation Control rod support having planar wear surfaces
EP0313365A3 (en) * 1987-10-21 1990-01-24 Westinghouse Electric Corporation Control rod support having planar wear surfaces
US5889832A (en) * 1995-12-26 1999-03-30 Framatome Nuclear reactor control cluster having removable rods

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Publication number Publication date
GB2179195B (en) 1989-01-18
GB8617203D0 (en) 1986-08-20
JPH0812266B2 (en) 1996-02-07
FR2586131B1 (en) 1990-06-15
JPS6235289A (en) 1987-02-16
FR2586131A1 (en) 1987-02-13
IT8621337A1 (en) 1988-01-31
IT1198008B (en) 1988-12-21
IT8621337A0 (en) 1986-07-31

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PCNP Patent ceased through non-payment of renewal fee

Effective date: 19920715