CN107068213A - Nuclear reactor passive triggering type safety device when being reduced extremely for amount of coolant - Google Patents

Nuclear reactor passive triggering type safety device when being reduced extremely for amount of coolant Download PDF

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Publication number
CN107068213A
CN107068213A CN201611047649.4A CN201611047649A CN107068213A CN 107068213 A CN107068213 A CN 107068213A CN 201611047649 A CN201611047649 A CN 201611047649A CN 107068213 A CN107068213 A CN 107068213A
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active unit
section
supporting section
supporting
neutron
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CN201611047649.4A
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CN107068213B (en
Inventor
丹尼斯·洛伦佐
伊莎贝尔·格纳特-狄来海
泽维尔·詹宁格罗斯
伯纳德·瓦伦丁
吉勒斯·阿瓦基安
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Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
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Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/28—Selection of specific coolants ; Additions to the reactor coolants, e.g. against moderator corrosion
    • 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
    • G21C17/022—Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
    • G21C17/025—Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators for monitoring liquid metal coolants
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08—Control 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
    • G21C7/10—Construction of control elements
    • G21C7/103—Control assemblies containing one or more absorbants as well as other elements, e.g. fuel or moderator elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
    • G21C9/027—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency by fast movement of a solid, e.g. pebbles
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/04—Safety arrangements
    • G21D3/06—Safety arrangements responsive to faults within the plant
    • 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

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

Abstract

It is used for the passive triggering type safety device that core answers heap the present invention relates to a kind of, the device is made up of a component, and the component includes：Protective case (200), have cooling agent longitudinally through；Active unit (100), along the longitudinal direction (3) translation is risen in protective case (200), and at least includes neutron-absorbing section；The active unit (100) includes the first supporting section (110) of relative neutron-absorbing section vertical misalignment, and protective case (200) includes the second supporting section (210).The formation of first supporting section and the second supporting section (110,210) as described above, and, when the first supporting section and the second supporting section (110,210) are oppositely arranged and flow longitudinally through the coolant flow Q of protective case (200)fMore than triggering flow QTriggeringWhen, active unit (100) that the power that cooling agent applies to active unit (100) is enough in supporting and protecting set (200) simultaneously keeps state of the active unit (100) under the supporting force configuration condition.

Description

Nuclear reactor passive triggering type safety device when being reduced extremely for amount of coolant
Technical field
The present invention relates to nuclear reactor technology field.More particularly, to one kind in reactor core primary Ioops cooling agent When the Traffic Anomaly of (also known as catalyst carrier) is reduced for interrupting in nuclear reactor in subactivity passive triggering type safety device.
The present invention is especially suitable for but be not limited to fast neutron reactor field, be used as one time especially with liquid metal sodium The fast neutron reactor of road cooling agent.
Background technology
In the reactor that reactor core is cooled down by cooling agent, such as liquid metal sodium cooling fast neutron reactor (RNR-Na), instead The control of answering property is realized generally by multiple safety devices that can stop neutron reaction.It is equipped with same reactor The redundancy and technological disparity of multiple safety devices should be able to be preferably minimized the possibility of above-mentioned stopping functional fault.
The operation principle of these safety devices is usually by absorbing rod (also known as neutron absorbing bar) whereabouts or is inserted into heap In core, to realize shutdown.Generally, these absorbing rods are translated rises in the protective case in reactor.Will be by absorbing rod and guarantor The component that sheath is constituted is arranged on around the component equipped with fissioner.These absorbing rods are used for the absorption pin for protecting inside Beam.
These must be cooled down and absorb pin.In fact, irradiation can raise the temperature of absorption pin.Especially, if using boron- 10 isotopes (10B) absorb neutron, and thermal power can be produced in the boron carbide material (B4C) for absorbing pin is constituted.However, in order to Ensure the various functions and/or mechanical strength of absorption needle member, it is necessary to limit the temperature of these components.Here it is suction must be cooled down The reason for narrowing.
So far, the main safety device of sodium cooling formula fast reactor (RNR-Na) is all active device, from this meaning For upper, absorbing rod insertion reactor core This move is the disappearance triggering by external electric controller or electric signal.In order to next For sodium cooling formula fast reactor (RNR-Na), intend exploitation passive auxiliary safety device, (active type is filled safely in main safety device Put) failure when use.These passive auxiliary safety devices are allowed in the case of without detection means or without operating personnel Make to fall in reactor core under absorbing rod.On the contrary, occurring the sensitive physical phenomenon of triggering device, (such as primary Ioops coolant flow is different Often reduce or temperature rise) when, it has to be possible to directly trigger the drop action of absorbing rod.
The present invention relates to the safety device of latter type.
In order to ensure the whereabouts of absorbing rod can be triggered by passive mode when primary Ioops coolant flow is reduced extremely Action, it has been proposed that multiple technical schemes.
It should be pointed out that primary Ioops refer to that its cooling agent directly takes the heat that heap in-core discharges out of in the loop of out-pile.One time Road directly with the component touch equipped with fissioner.
First technical scheme refers to documents FR1362783.In the technical scheme, it is proposed that pass through cooling agent The fluid produced and a guide pipe is circulated to realize the rising of absorbing rod；In this case, cooling agent will be by viscous resistance Power.By reducing coolant flow, absorbing rod can be made to fall in guide pipe；When not any coolant flow, absorbing rod is just Its shutdown position can be placed on.
It was verified that in above-mentioned " minor of drifting along " technical scheme, we can not accurately control the vertical position of absorbing rod Put, can not also prevent Endurance exercise and the correlated response change of absorbing rod.
Therefore, the technical scheme cannot ensure the drop action of understanding external trigger absorbing rod in no instance.
Second technical scheme refers to documents RU2069019.In the technical scheme, it is proposed that pass through absorbing rod Cooperation between the outer surface of neutron-absorbing section and protective case inner surface, sets an absorbing rod support region above reactor core.
It was verified that in the above-mentioned technical solutions, the cooling agent that absorption pin can not be flowed through component is sufficiently cool.Such as preceding institute State, absorbing pin cooling deficiency may adversely affect to the various functions and/or mechanical strength of its component.
Furthermore, it has been established that the stability of above-mentioned technical proposal is relatively poor.
Therefore, it is necessary to propose a kind of technical side for the shortcoming for being not present or can at least limiting above-mentioned known solution Case.
The content of the invention
The present invention relates to a kind of passive triggering type safety device, the core for taking out-pile out of by cooling agent for active region heat is anti- Heap is answered, the device includes component, the component includes：
Protective case, approximately perpendicularly extends in a longitudinal direction, has cooling agent to flow longitudinally through；
Active unit, along the longitudinal direction translation is risen in protective case, and at least includes neutron-absorbing section, the neutron Absorber portion at least includes neutron absorber material, and it extends mainly along longitudinal direction, and is configured to be flowed longitudinally through by cooling agent；
In addition, the active unit also includes the first supporting section, occurs vertical misalignment relative to neutron-absorbing section；
Also, protective case also includes the second supporting section；The formation of first supporting section and the second supporting section as described above, and And, if the first supporting section and the second supporting section are to be placed perpendicular to be transversely to the longitudinal direction on direction in opposite mode, So the first and second supporting sections will limit cooling agent free air space jointly, it is assumed that the space is S1 sections (or space j1), then：
- as the coolant flow Q for flowing longitudinally through protective casefLess than the cooling that reactor core This move is fallen under triggering absorbing rod Agent flux QTriggeringWhen, the power that cooling agent applies to active unit be enough supporting and protecting set in active unit and keep active unit Plumbness under supporting force effect；
- as flow Qf<QTriggeringWhen, the power that cooling agent applies to active unit is not enough to the active unit in supporting and protecting set, Also it is not enough to keep plumbness of the active unit under supporting force effect, therefore, the active unit will under gravity Decline the falling state until final position, i.e. absorbing rod along protective case；
If the first supporting section and the second supporting section are set not along horizontal direction in opposite mode, the first supporting section Cooling agent free air space, i.e. S2 section, such as S2 sections will be limited jointly with the protective case inner surface towards the first supporting section>S1 sections, then Even if flow Qf>QTriggering, the power that cooling agent applies to active unit be also insufficient to allow the active unit translation go back up to protective case In.
Therefore, the invention provides a simple, effective technical scheme, i.e., neutron-absorbing material is triggered by passive mode Expect the drop action of (typically absorbing pin), make to fall under it in reactor core active region of nuclear reactor.
Once coolant flow Qf<QTriggering, active unit will fall automatically, and coolant flow now is not enough to supporting The active unit.So, the neutron absorber material included in active unit will be fallen on down in the reactor core active region of reactor, from And stop neutron reaction.
Only coolant flow is reduced, and could realize above-mentioned triggering mode.Therefore, such safety device is completely passive 's.Different from the main safety device manually booted by control device automatic start or by operating personnel, passive triggering type is filled safely Put independent of automatically controlled triggering, so as to improve security.
For example, when control device failure, possibly the drop action of absorbing rod in the main safety device of active type can not be triggered, So, these absorbing rods can not be just fallen in reactor core down.On the contrary, according to the present invention, once coolant flow is decreased below Trigger threshold values QTriggering, active unit will fall.
In addition, according to the present invention, under the influence of changes in flow rate, the system of passive safety device can also be accurate Ground controls the upright position of active unit.
However, in the technical scheme that foregoing documents FR13622783 is proposed, it is impossible to control the position of active unit Put, can not also prevent Endurance exercise and the correlated response change of active unit, for example (primary circuit is cold under carrying state But agent flux is not zero) and power rating under (because when coolant flow bust, which jumps, the absorbing rod is increased).In fact, no matter inhaling How is the upright position of receipts rod, and the cooling agent circulation section between absorbing rod and protective case is all identical.If for example, activity is single Member is because coolant flow is reduced and falls, then, when subsequent coolant flow is increased up higher than activation threshold value, active unit It will be released, be raised to again above reactor core, so that the effect that stopping safety device centering subactivity is produced.
Within the scope of the invention, once active unit is because coolant flow is reduced extremely and is fallen, the first supporting section Just no longer it is oppositely arranged with the second supporting section, and active unit is also no longer gone up, even if coolant flow is increased above later Activation threshold value QTriggering, because the free air space between protective case and the first supporting section is too big, so that the power that cooling agent applies is not enough So that active unit is gone up.
In addition, working as Qf>QTriggeringWhen and when ensuring supporting functions, the first supporting section is relative to neutron-absorbing section vertical shift, the Two supporting sections are towards neutron-absorbing section but are not orthogonal to neutron-absorbing section, and on this basis, the present invention has many advantages, such as.It is true On, the supporting functions and refrigerating function of neutron-absorbing section are supporting.In fact, when ensuring supporting functions, according to embodiment, Cooling agent first passes through the free air space that two supporting sections being oppositely arranged are limited, the circulation then limited by neutron-absorbing section Space, or use opposite order.
Therefore, the supporting of active unit is by being ensured by all cooling agents of protective case.
In addition, the cooling of neutron absorber material can be by passing through the whole or at least big of neutron-absorbing section again by protective case Portion cooling agent ensures.Therefore, even if coolant flow is limited, the cooling of neutron absorber material (typically absorbing pin) Can be very effective.Under normal circumstances, the pin beam that pin is constituted about is absorbed by 19 in order to cool down, coolant flow is necessary Reach 2.5-3kg Liquid Sodiums/per second.When the metered flow for reaching cooling agent, i.e. 6kg Liquid Sodiums/per second, the present invention can be with complete Into substantial amounts of cooling work and can support movable unit.
However, in the technical scheme that foregoing documents RU 2 069 019 is proposed, it is necessary to shared coolant flow, To ensure the supporting functions and refrigerating function of neutron absorbing bar.As can be seen here, when reactor configuration is identical, we must develop Higher component flow, and there are two significant shortcomings in such mode：Reduce cooling effectiveness (total stream of reactor core of reactor Amount is not optimal)；If component is over cooled (compared to the fuel assembly of surrounding, the temperature difference is big), increase reactor core top structure Hot tearing risk.
In addition, according to the present invention, supporting functions are ensured by the independent segment containing neutron absorber material, can also be by setting Meter and the section that accurately controls of size ensure, to improve the accuracy and reliability of supporting functions.On the contrary, in documents RU In 2 069 019 technical schemes proposed, neutron-absorbing section provides hydraulic pressure and coordinates to generate supporting functions, and the chi of the supporting section Very little control is extremely complex, because the structure of neutron-absorbing section itself is also extremely complex, is related to multiple parts.However, the One and the inaccuracy (millimeter a few tenths of) at the second interval between supporting section, otherwise active unit can be hindered to rise influence It falls and (can produce influence to the availability of reactor), otherwise can during transient flow the Time-delayed trigger (safety of device Functional fault).
In addition, the present invention can at least have any one following feature：
- the first supporting section is supported by the outer surface of active unit.
- the second supporting section is arranged on the outer surface of protective case；
- protective case at least includes one the sleeve pipe in pipeline, also, second supporting section is formed by the sleeve pipe 's；
- the second supporting section (being typically sleeve pipe) uses overall processing mode.Like this, can be by the side of machining Formula, highly precisely manufactures the second supporting section.
- the first supporting section uses overall processing mode.Like this, can be by way of machining, very accurately Ground manufactures the first supporting section.
- longitudinal direction is vertical.
- the second supporting section only makees Longitudinal extending in a part for protective case longitudinal size.For example, the length of the second supporting section The ratio between length (more than base) of degree and protective case is 1/12.
Therefore, the accurate active unit of relative position could realize supporting only in protective case.
- neutron-absorbing section is included comprising many absorption pins in a tubule, the tubule, and these absorb pin and longitudinally prolonged Stretch, and include neutron absorber material.
- active unit includes pushing wall so that applies a thrust to the pushing wall by the cooling agent of protective case, and is somebody's turn to do One component of thrust can offset the weight of active unit.
The configuration of the device is as described above, then：When coolant flow cannot ensure the supporting of the active unit in protective case When, the active unit declines under gravity, until reaching home, so ensures that the falling state of absorbing rod.
The configuration of the device is as described above, then：In the falling state of absorbing rod, neutron-absorbing section is set along horizontal direction Put, and towards a region of protective case, the region is exactly the core space of orientating reaction heap reactor core active region.
- the first supporting section is located at the vertical lower of neutron-absorbing section.
Under supporting configuration condition, the first supporting section is located at the vertical lower of above-mentioned core space.In other words, the first supporting section Positioned at the upstream of neutron-absorbing section, relative to the coolant flow in protective case.
- the second supporting section is located at the vertical lower of above-mentioned protective case core space, and the reactor core of the core space orientating reaction heap Active region.
Therefore, the first supporting section is not in neutron current.So, the irradiation suffered by the first supporting section is conditional.So And, irradiate to micro- infringement caused by the metal material under neutron current, macro manifestations are change in size, in particular with irradiation Increase size expansion.Therefore, compared with the technical scheme of the first supporting section is set in neutron current, the present invention is able to ensure that it Feature, and the geometry in first region is not interfered with, this make it that the safety device is relatively reliable.
- the first supporting section is longitudinally disposed, and its neutron-absorbing between section across a compartmented.The compartmented Longitudinal stroke of the longitudinal length at least equal to active unit between bearing state and falling state.
- active unit includes the alignment pin of first supporting section of support.
Alignment pin is the part for absorbing stick pin.In the vertical, the alignment pin is equivalent to supporting section；In the horizontal, The alignment pin is equivalent to thrust wall.
- alignment pin is located at the bottom of active unit.
The lower end of-alignment pin helps to form a cooling agent thrust wall, to ensure the supporting of active unit.
- the first supporting section includes a supporting area being located in abutment wall, and the abutment wall is supported by alignment pin.
- the abutment wall is cylindrical.
- alignment pin is an integrated member, is generally made of one of following material or its alloy：EM10 ferrites-horse Family name's body stainless steel.Of course, it is possible to according to the service condition of reactor, it is considered to use other steel or metal (such as refractory metal).
- alignment pin is hollow, and which defines the internal capacity of a closing.
- the second supporting section is a sleeve pipe for being supported or being formed by protective case inner surface；
The inner surface of-sleeve pipe is cylindrical；
The distance between-internal surface of casing and alignment pin abutment wall define S1 sections and j1 intervals.
According to the first embodiment of the present invention, in the way of alone or in combination, passive triggering type safety device can at least have There is any one following optional feature：
- compartmented at least includes a pull bar, to ensure the mechanical connection between neutron-absorbing section and the first supporting section.
- compartmented at least includes two reinforcing members (preferably, three).These reinforcing members are typically pull bar, from mobile list The center of member starts, and extends radially the inwall of mobile unit；And since neutron absorber portion, extend lengthwise into first Hold section.
According to cross-sectional view, the area that pull bar and reinforcing member are occupied is less than 20%, it is preferable that less than 10%, and best Less than the 5% of neutron-absorbing section cross-sectional area.
Therefore, absorbing stick leg structure is conducive to cooling agent to be circulated in the safety device.
The absorption stick leg structure is equipped with pull bar and reinforcing member (preferably, three reinforcing members), and reinforcing member arrangement is in 120 °, have the following advantages that：There is provided the mechanical guide on whole stroke；Preferable mechanical stiffness；The liquid for making supporting area fail Press strong robustness；Lightweight, this is critically important for supporting；And the loss of low-load amount.
Compartmented at least includes a perforated pipe, to ensure the mechanical connection between neutron-absorbing section and the first supporting section.
Preferably, the perforated pipe includes multiple openings mainly extended longitudinally.
- these openings are distributed in the surface of whole perforated pipe.
- these openings are distributed on the longitudinal size of whole compartmented.
Therefore, absorbing stick leg structure is conducive to cooling agent to be circulated in the safety device.
The outer sectional dimension of whole perforated pipe is substantially equal to the outer sectional dimension of the first supporting section.Therefore, active unit Outer section at least include from neutron absorber portion to the first supporting section.
- the first supporting section is located at the vertical direction of neutron-absorbing section.
Under support conditions, the first supporting section is located at the vertical direction of protective case core space.
In this embodiment, if the first supporting section, which is located at, absorbs stick pin, that is, positioned at protection under support conditions The vertical lower of core space is covered, then the first supporting section is far from neutron current.It follows that the irradiation that the first supporting section is received It is conditional, to avoid the expansion that irradiation triggers.
According to reactor core and the distance on component top, supporting structure is positioned on absorption stick pin or pull bar by selection.
- the first supporting section is located at the top of absorbing rod between neutron-absorbing section, Longitudinal extending.Composition activity at the top of absorbing rod The upper end of unit.
According to one embodiment of the invention, the first supporting section is by the raised knot at the top of pull bar between neutron-absorbing section Structure is constituted, and is supported by active unit.The bulge-structure adds the cross section of active unit.
- active unit includes a pull bar, at least extends to neutron-absorbing section from the upper end of active unit.Also, it is described First supporting section is exactly the bulge-structure of a pull bar support between active unit upper end and neutron-absorbing section.
- the bulge-structure is arranged between two pull bars sections.
The lower end of-bulge-structure helps to form a cooling agent thrust face, to ensure the supporting of active unit.
- the bulge-structure is hollow, is provided with multiple cooling agent taps.
- the bulge-structure is the cylindrical wall of Longitudinal extending, and the second supporting section is one and supported by protective case inner surface Or the sleeve pipe formed.Space j1 between bulge-structure cylindrical wall outer surface and internal surface of casing, referred to as S1 sections.
According to one embodiment of the invention, in the way of alone or in combination, passive triggering type safety device can at least have Any one optional feature below：
The safety device includes an active unit damper, the dropping process for active unit.The damper bag Include：
- the first damping piece, is supported by active unit and is set to contact with cooling agent；
- the second damping piece, is supported by protective case and is set to contact with cooling agent.
Therefore the formation of first damping piece and the second damping piece in active unit as described above, falling and reaching Before stroke end position in state, the first damping piece will enter the second damping piece, and then, the first and second damping pieces are mutual Coordinate, to form a viscous damper.
According to one embodiment of the invention, the first supporting section and the first damping piece or the second supporting section and the second damping piece are Supported by same component.
Therefore, the component supported by protective case or active unit ensure that viscous damping function and supporting functions.
By this structure, the present invention has considerable advantage in terms of limitation is installed.In addition, this structure is solving a member There is special advantage in terms of size-constraints inside part.Therefore, the present invention can reduce for example necessary spy of key element The quantity for the element do not processed accurately.
The quantity of key element is reduced, the reliability of passive triggering type safety device is also just improved.
The manufacturing cost of the device can also be reduced simultaneously.
According to one exemplary embodiment of the present invention, the first supporting section and the first damping piece or the second supporting section and second Longitudinal height of damping piece (at least a portion) is identical.
In addition, following any feature can at least be had by being equipped with the present embodiment of damper：
The longitudinal direction height of first supporting section and the first damping piece or the second supporting section and the second damping piece (at least a portion) It is identical.
According to the embodiment for being equipped with damper, in the way of alone or in combination, passive triggering type safety device at least may be used With any one following optional feature：
- the second supporting section and the second damping piece are supported by same component.Protective case at least includes in sleeve pipe, protective case Supporting member formed by described sleeve pipe.
In this embodiment, the damping system being arranged on identical fixed part is devised, in order to support.It is such Embodiment has advantage as described below：
- for existing damping element, in the behaviour for height of the height higher than damping function requirement for carrying out supporting functions requirement When making, therefore length and stroke without changing active unit, will not produce influence to assembling height；
- in addition, a damping area need not be designed, because the function in damping area actually reduces effective damping, its is suitable In a boot section.Therefore, in this embodiment, it is not necessary to create new boot section, this is beneficial to the activity in damper Unit in face of jam, tremble equivalent risk when plug reliability (therefore being conducive to slowing down the speed of whereabouts).These jams, shake The equivalent risk that quivers is usually by the malformation of the lower device of irradiation, as caused by skew/deflection.According to the present embodiment, the solution party Case improves the reliability of damper movable part plug-in-sleeve part, and such insert action is the boot section constituted in sleeve pipe Interior completion.
In this embodiment, damping function and supporting functions (at least part function) are ensured by sleeve pipe.It is described to implement Example may have other advantages.
- sleeve pipe includes a chamber for filling cooling agent, and the chamber forms above-mentioned second damping piece.First damping piece An insert is formd, in order to insert above-mentioned chamber before active unit reaches its stroke end position and drive cooling Agent.
- sleeve pipe is disposed longitudinally between active unit bottom and neutron-absorbing section, it is preferable that be arranged on active unit bottom Between the top of active unit.
The shape of-the first damping piece is conducive to the chamber of its sleeve pipe.The chamber is circular, with horizontal ring Shape opening.By the opening, the first damping piece will be inserted before the stroke end position in reaching its falling state in active unit Enter the chamber.First damping piece forms a tubule, and the shape of its free end is conducive to it to enter chamber by above-mentioned opening Room.
- the second supporting section is formed by the inner surface of sleeve pipe.
- above-mentioned chamber is formed in sleeve pipe, with bottom.Second supporting section is formed by the inner surface of sleeve pipe, along vertical To setting at least partly towards chamber.
According to one embodiment：
Second damping piece, which forms a concave portions and had, fills cooling agent at least one chamber, chamber, the first damping Part forms an insert, in order to insert at least one above-mentioned chamber simultaneously before active unit reaches its stroke end position Extrude cooling agent.
Second damping piece formation one is used for the limiting section of active unit.
First damping piece is longitudinally between the lower end and active unit top of active unit, it is preferable that the first damping piece Longitudinal direction is located between active unit lower end and neutron-absorbing section.
First damping piece forms an insert, and the second damping piece one chamber of formation is easy to insert to enter chamber In.Preferably, the cross section of cavity is annular centered on the translated axis line of active unit, and opening from the upper end of chamber Extended lengthwise at mouthful positioned at the bottom of chamber.
The chamber is circular, with horizontal circular opening.By the opening, the first damping piece will be movable single Member inserts the chamber before reaching the stroke end position in falling state.Preferably, the first damping piece forms a tubule, The shape of its free end is conducive to it to enter chamber by above-mentioned opening.
The insertion body portion of first damping piece enters chamber, it is preferable that insert one end of the first damping piece can be certainly By insertion chamber, the other end is connected with the remaining part of active unit.Preferably, the first damping piece is connected directly between neutron The lower section of absorber portion.
The lasso that second damping piece is carried by internal surface of casing is formed, and the second supporting section is formed by the inner surface of sleeve pipe 's.
The chamber of second damping piece has bottom and with certain thickness, and the second supporting section is the inner surface shape by sleeve pipe Into.
Second supporting section and the second damping piece are oppositely arranged and at least a portion is highly identical in longitudinal direction.
According to the damping unit in another embodiment, in the way of alone or in combination, passive triggering type safety device is extremely There can be any one following optional feature less.
In the damping unit that the embodiment is provided：
The first supporting section and the first damping piece of the device are supported by same component, and the component forms movable single Alignment pin in member.
The outer surface of the alignment pin of the device defines the first supporting section and the first damping piece.
Protective case carrys out the translation of boot activity unit including at least one guide member；
Boot segment includes three cushion blocks, radial, be regularly distributed in around active unit translation shaft；
Boot segment includes the cushion block support ring being arranged on the protective case；
Boot segment is longitudinal positioning of in protective case, is easy to the movement of active unit, it is preferable that when active unit is falling When in state, guide member is located at the lower end of neutron-absorbing section；When active unit is not supported by, guide member is inhaled positioned at neutron Receive the upper end in area.
Therefore, the mutual cooperation between the outer surface of neutron-absorbing section and pad, it is ensured that living during whole service Moving cell is moved in sleeve pipe by accurate guiding.
Another aspect of the present invention is related to a kind of passive reaction terminating device, and it includes the passive trigger-type according to the present invention Safety device and for active unit position crawl gripping device.Grabbing device can move safety device, to incite somebody to action It is moved in ad-hoc location or it is returned to original position from ad-hoc location.
Another aspect of the present invention is related to a kind of nuclear reactor, and it includes fissible area and in the cold of its primary Ioops interior circulation But agent, and the device provided including at least one according to the present invention.
The nuclear reactor is preferably the reactor of fast neutron type.
Brief description of the drawings
Accompanying drawing is given as examples and does not limit the present invention.They only represent one embodiment of the invention.
- Fig. 1 is longitudinal section view of the passive handover security device that provides of embodiments in accordance with the present invention in lifting structure Figure.The passive handover security device i.e. when active unit is under the lift effect that the heat-exchange fluid for flowing longitudinally through protective case is produced Longitudinal sectional view.
- Fig. 2 shows the safety device in falling state, that is, active unit be not supported by but under gravity under The final position fallen in protective case.
- Fig. 3 includes Fig. 3 a and Fig. 3 b.Fig. 3 a show that active unit just declines and do not reach protective case under gravity In this state of final position in safety device.Fig. 3 b are the drawings in side sectional elevation of safety device, and the section is led positioned at protective case To between section and active unit neutron-absorbing section.
- Fig. 4 includes Fig. 4 a to Fig. 4 c.Fig. 4 a show Fig. 1.Fig. 4 b are the drawings in side sectional elevation of safety device shown in Fig. 1, and this is cutd open Face is located between spacer and supporting configuration.Fig. 4 c are the drawings in side sectional elevation of the safety device shown in Fig. 1, and the section is located at first Hold between section and expenditure configuration.
- Fig. 5 includes Fig. 5 a to Fig. 5 c.Fig. 5 a show Fig. 1.Fig. 5 b are the drawings in side sectional elevation of safety device shown in Fig. 1, and this is cutd open Face is located between spacer and supporting configuration.Fig. 5 c are the perspective views of the end points of safety device active unit shown in Fig. 1.
- Fig. 6 includes Fig. 6 a to Fig. 6 c.Fig. 6 a show Fig. 2.Fig. 6 b are the amplification views of safety device shown in Fig. 6 a, The section is located between damping unit and whereabouts configuration status.Fig. 6 c are the enlarged perspective and section of safety device shown in Fig. 6 a Figure, section is located between damping unit and whereabouts configuration status.
- Fig. 7 shows multiple operating procedures of the present invention.
- Fig. 8 includes Fig. 8 a and Fig. 8 b.Fig. 8 a are the profilographs according to safety device of the invention one.Fig. 8 b are shown The whereabouts configuration status of safety device shown in Fig. 8 a.
- Fig. 9 includes Fig. 9 a to Fig. 9 c.Fig. 9 a show Fig. 8 b.Fig. 9 b are the enlarged drawings of safety device shown in Fig. 8 a.Fig. 9 c It is the drawing in side sectional elevation of safety device shown in Fig. 8 a, the section is located between sleeve pipe and perforated pipe.
- Figure 10 includes Figure 10 a to Figure 10 c.Figure 10 a are the profilographs according to safety device of the invention one.Wherein First supporting section is located above the neutron-absorbing portion, and Figure 10 b are Figure 10 a enlarged drawings, and the section is located at first and second Hold between section.Figure 10 c are Figure 10 b perspective views.
- Figure 11 is the enlarged drawing of the first and second supporting sections cooperation in one embodiment of the invention.
Above-mentioned accompanying drawing is principle schematic, readily appreciates the present invention, is not necessarily been drawn to scale.Especially, first Holding the interval between section and protective case inner surface or internal surface of casing may not exist in practice.
Embodiment
In nuclear reactor, the heat transfer of fissile region gives at least one cooling agent.Generally, device includes several components. A part of component includes fissile material, and other components include control rod, for subactivity in control.Remaining component is used for Passive triggering type safety device is constituted, when reactor operation is abnormal, to prevent or slow down middle subactivity.
The passive triggering type safety device that embodiments of the invention are provided is described in detail referring now to Fig. 1 to 6.
The device mainly includes a protective case 200 for being used to be inserted into the reactor core of reactor.The protective case 200 A part is as core space 240, and the area is towards horizontal direction, longitudinal direction of the horizontal direction perpendicular to the fissile region 10 of reactor Direction 3.Because protective case 200 is fixed in the operating process of reactor, the core space 240 is always located in fissile region 10 Lower section.
The protective case 200 extends in longitudinal direction 3.In operating process, the longitudinal direction is inclined in the horizontal direction. Under normal circumstances, as illustrated, the longitudinal direction 3 is vertical.
The protective case 200 extends from upper end 202 and component bottom 204, and the upper end can be crawled processing assembly, described group Part bottom is used to make the component be located at the bottom of reactor, and ensures the supply of cooling agent such as liquid sodium.
Protective case 200 is used to cause cooling agent to flow transversely through the protective case 200 from the entrance 205 positioned at component bottom 204, Then reach positioned at the outlet 203 of upper end 202, and illuminated by supply lamp 205.
Preferably, the protective case 200 includes an overcoat formed by part hexagon pipe 201.The longitudinal wall of protective case 200 is Sealedly.
The passive triggering type safety device also includes active unit 100, and the active unit is arranged in protective case 200 It is interior, and moved along the longitudinal direction 3 of protective case.In nuclear industry, active unit is also referred to as rod.The main edge of active unit 100 Longitudinal direction 3 to extend, therefore, as illustrated, performing operation in vertical direction.Active unit 100 is extended to from top 101 Bottom 103.Active unit includes the neutron-absorbing section 130 being located between top 101 and bottom 103, and it includes neutron-absorbing material Material.
For the fast neutron nuclear reaction heap cooled down by liquid metal, neutron absorber material can be boron carbide (B4C), it is rich Collection is a little10B.Alternatively, the neutron absorber material can also be hafnium sill.Because the density of material is high, therefore shortens Fall time, it is to avoid the lower release gas of irradiation, and then expansion is avoided, the stain resistance energy of the material will not significantly drop It is low.Or, the neutron absorber material can also be refractory boride absorbing material, for example, HFB2And TiB2, its fusing point is about 3300℃.Europium hexaboride EuB can also be used6Or Eu2O3, under the radiation, they will not discharge gas, and these materials Absorbability it is strong.
In pressurized-water reactor, the absorbing material can be, e.g. hafnium compound, Dy11B6、Gd11B6、Sm11B6、 Er11B4, natural HfB2Or natural TiB2。
The neutron-absorbing section 130 generally includes the absorbability pin beam 131 of encapsulating in main body 104.Pin beam 131 is main along vertical Extend to direction 3.Cooling agent flows transversely through the arrival outlet 203 of neutron-absorbing section 130 to cool down neutron suction from component bottom 204 Receive section.From Fig. 3 b it is clear that the mechanical fastener 132 of neutron-absorbing section 130 is located between absorbability pin beam 131.This The passage 133 that a little connectors 132 are defined makes its cold for making the cooling agent of circulation neutron-absorbing section 130 flow transversely through the passage But.
In the figure 7, the top 101 of movable unit 100 coordinates with claw hook type gripping device 300, for operation during, make Active unit 100 in protective case 200 is located at suitable position.
Active unit 100 also includes the first supporting section 110, for when the flow of cooling agent is less than predetermined threshold, triggering The drop action of active unit 100.This function will be described in detail later.
Active unit 100 also includes the first damping piece 140, matches somebody with somebody with the second damping piece 220 of the setting on protective case 200 Close, for providing damping for the active unit 100 in dropping process.The first damping piece 140 and the second damping is described in detail below Part 220.
Illustrate the passive trigger mechanism of active unit 100 below.By the mechanism, when the Traffic Anomaly of cooling agent reduces simultaneously Less than stroke activation threshold value QTriggeringWhen, active unit 100 declines under gravity.Therefore, under active unit 100 is reachable Fall the final position of process, neutron-absorbing section 130 is relative to the fissile region 10 of reactor and the core space 240 of protective case 200 Laterally.
First supporting section 110 of active unit 100 has the outer wall relative with the inwall of protective case 200.In protective case 200 The cross section of wall narrows, and forms the second supporting section 210.In a longitudinal direction, the change of the cross section of limitation protective case 200 It is narrow.Generally, the length of the Longitudinal extending of the second supporting section 210 is less than the 1/5 of the length of protective case 200, it is preferable that less than 1/10, More preferably, less than 1/15.Specifically, the length and protective case 200 of second supporting section 210 are located above reactor bottom Ratio between length is about 1/12.
The space that the inner surface of first supporting section 110 and protective case 200 is limited can make cooling agent in protective case 200 Flowing.When the first supporting section 110 is laterally set relative to the second supporting section 210, the space reduces.
Preferably, relative to neutron-absorbing section 130, the length travel of the first supporting section 110.In the reality shown in Fig. 1-9 and 11 Apply in example, the first supporting section 110 is located at the lower section of neutron-absorbing section 130.The advantage of the embodiment is described further below.According to another Embodiment, as shown in Figure 10, the first supporting section 110 are located in neutron-absorbing section 130.In above-mentioned all embodiments, first Supporting section 110 is not located in neutron-absorbing section 130, and it is maintained a certain distance with neutron-absorbing section on longitudinal direction 3.
First supporting section 110 and the second supporting section 210 are set as follows：First supporting section 110 and the second supporting section 210 are oppositely arranged being transversely to the machine direction on the horizontal direction in direction 3, to form whereabouts.First supporting section 110 and the second supporting section The 210 common spaces limited for cooling agent circulation.The space has S1 sections, if the outer sky placed of whole active unit 100 Between j1 be regular, then the interval can limit the space.
By setting the first supporting section 110 and the second supporting section 210, make it opposite in other words, it is described under supporting role S1 sections (or space j1) is set in the following way：
- as the coolant flow Q for flowing longitudinally through protective case 200fMore than predetermined flow QTriggeringWhen, cooling agent is single to activity The power that member 100 applies is enough to offset the gravity of the active unit 100 in protective case 200, active unit is located under the supporting force In plumbness.
Specifically, active unit 100 also includes at least one pushing wall 117, pushes wall and is based on it perpendicular to cooling agent Flow direction on projection (being determined according to transverse projection) surface area be more than zero,.Cooling agent applies to thrust wall 117 The quality of power and active unit 100 is opposite.
- as flow Qf<QTriggeringWhen, the power that cooling agent applies to active unit 100 is not enough to the work in supporting and protecting set 200 Moving cell 100, is also not enough to keep active unit 100 to be in plumbness under the conditions of the supporting force.Therefore, the active unit 100 under gravity, will decline along protective case, until reaching stroke end position.On the position, neutron-absorbing section 130 is opposite with reactor core 10, to stop or slow down middle subactivity.
The supporting section 210 of first supporting section 110 and second or its forward surface are set in the following way：When first Hold the supporting section 210 of section 110 and second laterally it is opposite when, the first supporting section 110 and be opposite in the interior of the first supporting section 110 Wall collectively defines the space circulated for cooling agent, and the space has S2 sections, and S2>S1 (or space j1>j1).With the S2 Section or S1 sections define in the following way：If the flow Q of cooling agentfMore than trip value, (according to the rules, it is rated power Flow down value 110%) when, the power that cooling agent applies to active unit 100 be not enough to supporting and protecting cover 200 in active unit 100, therefore, when being declined with normal speed, absorbing rod can not be discharged from fissile region 10, can only be by gripping device 300 separate absorbing rod from fissile region.
Therefore, according to above-described embodiment, the present invention proposes one kind by the first supporting section 110 and the second supporting section 210 The hydraulic support area cooperatively formed below reactor core scheme.When active unit 100 is not supported by, hydraulic support area is not Start.
The safety device that the present invention is provided is firm, efficient, practical.In fact, it has the following advantages：
The section hydraulic area formed by the first supporting section 110 is located at the lower section of neutron-absorbing section 130, hydraulic pressure (supporting) and heat Work fluid (beam cooling) functional areas are not coupled, but series connection.This cooling for causing pin beam 131 and the lifting of active unit 100 are fine Control；
So the flow velocity that component is distributed can essentially be used for being lifted and being cooled down.Therefore, when radial clearance and supporting area During the area equation of domain, in theory, the supporting region of stick pin is absorbed than positioned at the amount of coolant needed for the lifting zone of neutron-absorbing section It is few, that is to say, that absorbing rod can support heavier (or equivalent) material in itself；
In the insertion stage, no matter where pin beam is located at longitudinal direction, and the cooling of pin beam 131 is identical.
The flexibility of the manufacturing tolerance of lifting zone part：In lifting zone, if the first supporting section 110 and the second supporting section 210 are formed by countless segments, it has to be possible to easily it was observed that the radial clearance of several millimeters (being the 1/10 of manufacturing tolerance)；
The design of pin beam 131 has certain freedom：The change of the size of pin beam 131 does not interfere with the first supporting section 110 With the size of the second supporting section 210.Actual development (work of the project) is not only is it beneficial to, and is conducive to extending reactor Life-span；
To provide facility in terms of calculating；And
In the dropping process of active unit or in suspended state, failure is easily-controllable caused by mechanical problem.
The invention is not limited in the space that cooling agent circulation is limited with cylindrical wall is S1 sections.As long as can guarantee that supporting Function and triggering are fallen, and it can be any shape.
Preferably, protective case 200 includes the interior sleeve pipe 211 for being arranged on hexagon pipe 201, the sleeve pipe 211 formation second Supporting section 210.By applying active force for sleeve pipe 211, the purpose that hexagon pipe 201 applies active force can be reached for.Compare In applying active force directly to hexagon pipe 201 in the prior art, present approach reduces manufacture complexity and cost.For example, logical The sleeve pipe 211 is crossed, can be very good to control the size of protective case.
Preferably, the embodiment according to Fig. 1-9 and Figure 11, the first supporting section 110 is the positioning of active unit 100 Pin 112 is defined.Alignment pin 112 is arranged on bottom 103.At least a portion thrust wall 117 is formed on alignment pin 112 and bottom 103. In the described embodiment, the pushing wall 117 is the bottom 103 formed by plane and extends to alignment pin 112 along bottom 103 Inclined-plane is constituted.
As described above, by the thrust wall 117, the heating fluid for flowing through the protective case 200 is applied to active unit 100 The one-component of thrust be used to offset the gravity of active unit 100.This thrust is thrown in the transverse direction positioned at the thrust wall On the face of shadow, and for the pressure differential between the top and bottom of the first supporting section 110 of balance.
The alignment pin 112 is used for the part for limiting the space between active unit 100 and protective case 200.Such as embodiment Shown, the first supporting section 110 is cylindrical.The alignment pin is an integrated member, generally using following material or its conjunction Gold：Such as EM10 ferrite-martensites stainless steel.Other Steel materials or metal, such as refractory metal can also actually be used Selection Deng, material is determined according to the practical operation condition of real reaction heap.
Preferably, alignment pin 112 can be made on a large scale, to more precisely control the size of alignment pin, moreover, this system S1 sections of restriction is also beneficial to as method.
In one embodiment, alignment pin is solid member.
According in still further advantageous embodiment, alignment pin is hollow, thus weight is lighter.Can by machining or its Other party legal system makes alignment pin.In order to avoid producing depression at the edge at the top of alignment pin, one is additionally arranged at the bottom of in alignment pin Plug.
Preferably, in the embodiment shown in Fig. 1-9 and Figure 11, the first supporting section 110 is vertically positioned at neutron-absorbing section 130 Lower section.Therefore, in bearing state, alignment pin 112 is located at the lower section of reactor core.When flowing of the cooling agent 5 in protective case 200 When, the first supporting section 110 is located at the top of neutron-absorbing section 130.
In one alternate embodiment, the first supporting section 110 is vertically positioned at the top of neutron-absorbing section 130.It describes tool Body reference picture 10.
The embodiment that first supporting section 110 is vertically positioned at the lower section of neutron-absorbing section 130 has many advantages, such as.
Because the first supporting section 110 is not in neutron current, the irradiation suffered by the first supporting section 110 is limited. However, irradiation is change in size to the macro manifestations of micro- infringement caused by the metal material under neutron current, in particular with spoke According to the increase size expansion of amount.Therefore, compared with the technical scheme of the first supporting section is set in neutron current, this programme will not shadow The geometry in first region is rung, and ensures its feature, this make it that the safety device is relatively reliable.
Reference picture 11, it is described in detail herein by determining power that cooling agent produces to realize the scheme of lifting.
Figure 11 shows the second supporting section 210 formed by sleeve pipe 211, and the alignment pin 112 defines active unit 100 The first supporting section 110, its longitudinal wall is towards the longitudinal wall of sleeve pipe 211, and its thrust wall 117 bears the lifting force produced by cooling agent. In the figure, the diameter D211 of the diameter D112 of alignment pin and the internal channel formed by sleeve pipe is illustrated, and the two diameters Between gap j1 be also shown as.Also illustrate the flow direction of cooling agent 5 and the pressure P1 of the upper end of sleeve pipe 211 with in the figure The pressure P2 at end.In lifting process, L211 represents longitudinal length.Along this direction, the first supporting that sleeve 211 is defined Section 110 faces the second supporting section 210.
It is based on such as the lifting force produced by the pressure drop between hydraulic pressure Cooperative District and the part of a diameter of D112 alignment pin Lower parameter：Length L112-211, diameter D211, radial clearance j1=D211-D112.In addition, in fact, when the positioning of active unit 100 After mechanism is separated with grabbing device 300, the distance that active unit 100 is moved in the process is L112-211.This is conducive to activity The lifting of unit, makes reaction more preferably carry out, and makes device reliably and stably.
After separation, inevitably, supporting region will support the whereabouts of active unit, even in flow QfValue be still higher than Trigger value QTriggering.The presence of separation is caused by the unstability of system, and unstability is by geometry/machinery (in protective case Active unit misalignment), hydraulic pressure (such as hydraulic pressure disturb, vibration) or other reasonses are in gap between pin and sleeve pipe (for example, deposit In impurity) cause.
According to metered flow QNWith activation threshold value QTriggering, in the dropping process of active unit 100, those skilled in the art Know, the size of the first supporting section 110 and the second supporting section 210, especially its cross section and length, keep constant.
Specifically, the F of effect on the active unitThrustIn Q when can make active unitfMore than QTriggeringWhen it is elevated, and One supporting section 110 and the second supporting section 210 are opposite.The thrust is as follows：
FThrust=FPressure+FFrictional force
Wherein：
-FFrictional forceRepresent the viscous drag of hydraulic pressure Cooperative District.Embodiment as shown in figure 11, the frictional force is depended primarily on Length L211, coolant viscosity and interval j1 intervals, wherein, j1=D211-D112.
-FPressureRepresent coolant and apply pressure (usually from the alignment pin 112 of thrust wall 117) on the projection surface and cold But the application pressure P on the projection surface of liquid1.Embodiment as shown in figure 11, applies the size master of pressure on the projection surface To depend on diameter D112With pressure P1。
Therefore, FThrustAt least to offset the quality of absorbing rod, that is to say, that the buoyancy is subtracted from the thrust.
According to one embodiment, the longitudinal direction of the first supporting section 110 is located under neutron-absorbing section 130, and with neutron-absorbing section Between distance away to form compartmented 120.The length of distance piece is equal in active unit lifting and dropping process Stroke.It ensure that the first supporting section 110 will not be located at reactor core.No matter the first supporting section 110 is located at where, can all have as above Described advantage.Moreover, when the first supporting section 110 is in neutron current, the spoke suffered by the first supporting section 110 can also be reduced The amount of penetrating.
Compartmented 120 can be performed according to various embodiments.Embodiment as shown in Fig. 1-9 and Figure 11, compartmented bag A pull bar 122 and a reinforcing member 121 are included, to ensure the mechanical connection between neutron-absorbing section 130 and the first supporting section 110. Preferably, as shown in Figure 4 b, compartmented 120 includes three reinforcers 121, and the reinforcing member 121 is from the center of mobile unit 100 Start to extend radially, and extend lengthwise into since neutron absorber portion 130 the first supporting section 110).Under the structure has Row advantage：Realize the mechanical guiding in whole stroke；Improve mechanical strength；Weight is reduced, this is extremely important to supporting； The pressure loss is small；Designed without complicated hydraulic pressure.
Fig. 8 and 9 shows the embodiment of compartmented 120.Compartmented 120 includes perforated pipe 123.Perforated pipe 123 has vertical To the opening 124 of extension.These openings 124 are distributed in the whole profile of perforated pipe 123 and the whole longitudinal size of compartmented 120 On, therefore, cooling agent can reduce the energy consumption of neutron-absorbing section 130 through these openings 124, and be allowed to cool.
According to embodiment, perforated pipe 123 has and pull bar and its reinforcing member identical advantage.However, perforated pipe needs more Advanced hydraulic pressure and mechanical technique.
By the absorbing rod mechanism including gripping device 300, active unit 100 becomes simply may be used in the crawl of operating position OK.The gripping device is used for the head 101 for capturing active unit.Hereinafter, in order to ensure the dropping process of active unit 100 It is to realize that the mechanism is only used for crawl by passive triggering.
The operation principle of passive triggering type safety device according to the present invention is described referring now to Fig. 7.
At the drop-off positions shown in Fig. 7 a, between active unit 100 and protective case 200, more specifically respective supporting section Area is not activated between hydraulic pressure cooperation between (110,210).
Before reacting, by the absorbing rod mechanism including gripping device 300, it is accurate that active unit 100 carries out whereabouts It is standby.That is, when reactor is activated, active unit 100 has been carried out whereabouts and prepared.The absorber portion of the active unit 100 130 In reactor core.The gripping device grasps the top 101 (as shown in Figure 7b) of active unit, is made with lifting the active unit 100 Its is vertical.Lifting process is as shown in Figure 7 c.
In above-mentioned steps, coolant flow QfIt is consistent with the processing speed value of reactor, and less than being mentioned below Rate of release.
Then, by absorbing rod mechanism, when making active unit hanging, coolant flow QfIncrease, (as shown in figure 7d).
QfAt least equal to QTriggering≤QRelease, it is preferable that work as QTriggering<QReleaseWhen it is safer, now gripping device 300 is opened, absorb Rod mechanism releasing activity unit 100, as seen in figure 7e, wherein, QRelease<QN。
Preferably, when active unit 100 is lifted by the 300 of gripping device, it has first be located in protective case 200 Hold the supporting section 210 of section 110 and second.QReleaseThe power of generation is used to lift active unit 100.
As long as QTriggering<Qf, QfIts rated value can be continued to increase to, to ensure the whereabouts of active unit 100, such as Fig. 7 E institutes Show.
If however, Qf<QTriggering, QfThe power of generation can not lift active unit 100, and active unit is in gravity (such as Fig. 7 f institutes Show) in the presence of under fall on the final position of its stroke, as shown in the figure shown in 7g.
Therefore, when transient flow value not protected in primary Ioops is decreased below the flow for part distribution suddenly, Hydraulic pressure cooperation stops so that under gravity, the active unit 100 and absorber material 130 declined with passive triggering mode Insert reactor core 10.
With reference to Figure 10 a, 10b, 10c, in one alternate embodiment, the first supporting section 110 is vertically positioned at neutron-absorbing section 130 top.Therefore, the first supporting section 110 is vertically positioned at the top of core space 240 of protective case 200, therefore positioned at reactor The top of core 10.Specifically, the first supporting section 110 is located between the top 101 of active unit 100 and neutron-absorbing section 130.
According to one embodiment, the first supporting section 110 is that the projection 115 on pull bar 102 is constituted.Projection 115 is in work Extend between the top 101 of moving cell 100 and neutron-absorbing section 130.Therefore, projection 115 is located between the two ends of pull bar 102.Such as Shown in Figure 10 a, by compartmented 120, projection 115 and the neutron-absorbing section 130 of the first supporting section 110 keep certain distance.It is convex Playing 115 has lower end, to form the thrust wall 117 for cooling agent, realizes the lifting of active unit 100.
Preferably, projection 115 is hollow, is provided with multiple cooling agent taps (116,118).In this some holes, on Cooling agent tap 118 is located at the upper end of projection 115, and at least one lower cooling agent tap 116 is located at the lower end of projection 115. Projection 115 is with the cylindrical wall for being Longitudinal extending, and the second supporting section 210 is the sleeve pipe 211 formed by protective case 200；It is convex The space risen between the outer surface of 115 cylindrical wall and the inner surface of sleeve pipe 211 is referred to as S1 sections, is circulated for cooling agent.
Preferably, safety device includes the damper of active unit 100, the dropping process for active unit.
The damper includes the first damping piece 140, is supported by active unit 100 and is set to contact with cooling agent, the Two damping pieces 220, are supported by protective case 200 and are set to contact with cooling agent.
First damping piece 140 and the second damping piece 220, which are formed so that, to fall in active unit 100 and falls in its arrival Before stroke end position under configuration status, the first damping piece 140 will enter the second damping piece 220, then, the first damping piece 140 and second damping piece 220 work in coordination, to form a viscous damper.
Preferably, the second damping piece 220 forms the locating part of active unit 100.Therefore, it is to avoid active unit 100 with Bottom wall 206 positioned at the lower end of the set 200 of protection is collided.
Embodiment according in Fig. 1-6, Fig. 8-9, the first damping piece 140 of the device is longitudinally disposed at activity Between the bottom 103 of unit 100 and neutron-absorbing section 130, specifically in the lower end of neutron-absorbing section 130.In another embodiment In, the second damping piece 220 forms a concave portions and with least one chamber 225, and the cross section of chamber 225 is with movable single Annular centered on the translated axis line of member, and extend lengthwise at the opening 226 of the upper end of chamber 225 bottom of chamber 225 Portion 227.
First damping piece 140 forms insert, in order to be inserted before active unit 100 reaches its stroke end position Above-mentioned chamber 225.
First damping piece 140 forms a tubule, and the shape of its free end 141 is conducive to it to enter chamber.Such as Fig. 6 b With shown in 6c, the other end and the active unit 100 of the pipe are mechanically connected.Preferably, the end and the lower end phase of neutron-absorbing section 130 It is adjacent.
Chamber 225 is substantially on the central axis of active unit 100, and the size of insertion is corresponding with the size of chamber 225, So that during insertion, the cooling agent in chamber 225 is displaced, viscous force, the insertion for preventing insert are produced.Specifically The establishment of ground, the chamber 225 and insert size is used to ensure that enough viscous damping forces, prevention active unit can be produced Fallen under 100 before its stroke end position.
Preferably, chamber 225 is formed in the thickness of sleeve pipe 211.Preferably, the second supporting section 210 is also by sleeve pipe 211 Formed.
Therefore, sleeve pipe 211 has two walls, and each wall provides a very specific function：
- when flow is sufficient, coordinate in a wall of sleeve pipe 211 with active unit, to realize that it is provided；
- when Traffic Anomaly reduces, another wall of sleeve pipe 211 ensures damping force, prevents to fall under active unit 100 Before its stroke end position.
Preferably, the second damping piece 220 is used to provide viscous damping, and the second supporting section 210 has elevating function, the second resistance Damping member and the second supporting section are at least partly oppositely arranged in a longitudinal direction, i.e. on horizontal level, and they are in same height Degree.Such setting is very beneficial for realizing size Control.Moved from Fig. 4 c and Fig. 5 the b liftings that can be seen that active unit 100 Make to complete between chamber 225 and space j1.In the present embodiment, it is necessary to which the number for carrying out the critical component of retrofit is reduced .In addition, save considerably space.
In this embodiment, the damping and enhanced feature that sleeve pipe 211 is provided have advantage as described below：
- for existing damping element, in the behaviour for height of the height higher than damping function requirement for carrying out enhanced feature requirement When making, therefore length and stroke without changing active unit, will not produce influence to assembling height；
- in addition, a damping area need not be designed, because the function in damping area actually reduces effective damping, its is suitable In a boot section.Therefore, in this embodiment, it is not necessary to create new boot section, this is beneficial to the activity in damper Unit in face of jam, tremble equivalent risk when plug reliability (therefore being conducive to slowing down the speed of whereabouts).These jams, shake The equivalent risk that quivers is usually by the malformation of the lower device of irradiation, as caused by skew/deflection.According to the present embodiment, the solution party Case improves the reliability of damper movable part plug-in-sleeve part, and such insert action is in drawing that sleeve pipe 211 is constituted Lead what is completed in area.
According to unshowned embodiment, damping function can also between pin 112 and protective case 200 with provide, it is excellent Selection of land is provided by bottom wall 206.
Therefore, the first supporting section 110 and the first damping piece 140 are limited by the outer surface 113 of the pin 112 of active unit 100. Therefore, in the present embodiment, the same parts that the lifting and damping function are carried by active unit 100 are provided, the part It can be alignment pin 112.Bottom wall 206 is preferably attached to the inside of sleeve, for example, be fixed on bottom 204.
As shown in the preferred embodiment in Fig. 1 to 6 and Fig. 8-10, the safety device includes：At least one guide section 230, it is used for boot activity unit 100 and shifted in protective case 200.As shown in Figure 3 b, guide section 230 is included by least two At least one guide section 230 individual, be preferably made up of three cushion blocks 231, shifting of the cushion block 231 on active unit 100 Moving axis is symmetrical.Cushion block 231 in Fig. 3 b is separately from each other with 120 ° of arranged for interval.Preferably, guide section 230 is by it Side defines that the cushion block race ring of cushion block 231 is constituted.
Guide section 230 is longitudinally arranged in protective case 200, in being reached when mobile unit 100 is in lifting state Sub- absorber portion 130.Therefore, the cooperation between the lateral surface and the cushion block 231 of neutron-absorbing section 130 ensure that active unit 100 accurate in protective case 200, reliable displacement guiding.
But, above-described embodiment is not restricted.
In view of foregoing description, it will be apparent that, the invention provides particularly reliable and safe solution, work as cooling agent When Traffic Anomaly is reduced, absorbing rod is set to fully rely on passive mode whereabouts.
The present invention is not limited to the embodiment of foregoing description, extends to all implementations covered by claims Example.
Reference
1. the reactor core of 3. longitudinal direction of device, 5. cooling agent 10.
100. the top of active unit 101. bottom of 102. pull bar 103.
104. the alignment pin of 110. first supporting section of absorbing rod 112.
113. the tap of 115. bulge-structure of outer surface 116.
117. the compartmented of 118. head space of thrust wall 120.
121. the perforated pipe of 122. pull bar of reinforcing member 123.
124. the 130. neutron-absorbings section 131. that is open absorbs pin
132. the damping piece of 133. coolant channel of connector 140. first
The six angle pipes of 141. pipe end, 200. protective case 201
Assemble pin in the outlet 204. of 202. top 203.
The supporting section of 205. power supply indicator, 206. wall 210. second
The damping piece of 211. sleeve pipe, 212. inwall 220. second
225. chambers 226. opening, 227. chamber bottoms
The core space of 230. guide section, 231. cushion block 240.
300. fastener

Claims (36)

1. passive triggering type safety device (1), is to take out-pile out of by cooling agent at least part heat including heap in-core Nuclear reactor, the device includes component, and the component includes：
● protective case (200), (3) approximately perpendicularly extend the protective case in a longitudinal direction, for cooling agent longitudinally through；
● active unit (100), the active unit can be risen in protective case (200) in (3) translation along the longitudinal direction, and extremely Include neutron-absorbing section (130) less, the neutron-absorbing section at least includes neutron absorber material, the main edge of neutron-absorbing section Longitudinal direction (3) extension, and configure can by cooling agent longitudinally through；
Characterized in that, the active unit (100) includes the first supporting section (110), the protective case (200) includes second Hold section (210)；First supporting section and second supporting section (110,210) are formed so that：
If first supporting section and second supporting section (110,210) be set and be arranged in opposite mode it is vertical Directly on the horizontal direction of longitudinal direction (3), then first and second supporting section (110,210) limits cooling agent circulation jointly Space, if the space is S1 sections, then：
- as the coolant flow Q for flowing longitudinally through protective case (200)fLess than the cooling that reactor core This move is fallen under triggering absorbing rod Agent flux QTriggeringWhen, the power that cooling agent applies to active unit (100) is enough the active unit (100) in supporting and protecting set (200) And keep plumbness of the active unit (100) under the supporting force configuration condition；
- as flow Qf<QTriggeringWhen, the power that cooling agent applies to active unit (100) is not enough to the activity in supporting and protecting set (200) Unit (100), is also not enough to keep plumbness of the active unit (100) under the supporting force configuration condition, the active unit (100) it will decline along protective case gravity, until reaching stroke end position, i.e. absorbing rod whereabouts configuration status；
If first supporting section and the second supporting section (110,210) are set not along horizontal direction, then first supporting Section (110) and the common restriction cooling agent circulation sky of protective case (200) inner surface (212) towards first supporting section (110) Between, i.e. S2 sections, at S2 sections>At S1 sections, even if flow Qf>QTriggering, the power that cooling agent applies to active unit (100) is also not enough to The active unit (100) translation is set to go back up in protective case (200).
2. the device (1) according to the claims, wherein, first supporting section (110) is by the active unit (100) outer surface support.
3. the device (1) according to any of the above-described claim, wherein, the protective case (200) at least includes sleeve pipe (211), second supporting section (210) is formed by described sleeve pipe (211).
4. the device (1) according to any of the above-described claim, wherein, first supporting section (110) is located at the neutron The vertical lower of absorber portion (130).
5. the device (1) according to any of the above-described claim, wherein, second supporting section (210) is located at the protection The vertical lower of set (200) core space (240), and the reactor core active region (10) of the core space orientating reaction heap.
6. the device (1) according to any one of above-mentioned two claim, wherein, first supporting section (110) is along vertical To setting, and its neutron-absorbing between section (130) across compartmented (120)；The longitudinal length of the compartmented is at least Equal to longitudinal stroke of the active unit between supporting configuration status and whereabouts configuration status.
7. the device (1) according to any one of above three claim, wherein, it is described that the active unit includes support The alignment pin (112) of first supporting section (110).
8. the device (1) according to the claims, wherein, the alignment pin (112) is located at the active unit (100) Bottom, and the lower end (103) of the alignment pin (112) helps to form cooling agent thrust wall (117), to ensure the activity The supporting of unit (100).
9. the device (1) according to any one of above-mentioned two claim, wherein, the alignment pin (112) is cylinder Integrated member, generally using one of following material or its alloy：Ferrite-martensite stainless steel, EM10 ferrite-martensites Stainless steel, refractory metal etc..
10. the device (1) according to any one of being required above three profit, wherein, second supporting section (210) is by institute State the support of protective case (200) inner surface or the sleeve pipe (211) formed；Described sleeve pipe (211) inner surface and the alignment pin (112) The distance between abutment wall is defined to S1 sections.
11. the device (1) according to any one of aforementioned four claim, wherein, the alignment pin (112) is hollow , and define the internal capacity of closing.
12. the device (1) according to any of the above-described claim, wherein, first supporting section (110) is longitudinally disposed, And its neutron-absorbing between section (130) across compartmented (120)；The compartmented (120) at least includes pull bar (122) With reinforcing member (121), to ensure the mechanical connection between neutron-absorbing section (130) and first supporting section (110).
13. the device (1) according to the claims, wherein, the compartmented (120) at least includes two reinforcing members (121), preferably three, these reinforcing members (121) are extended radially since the center of the mobile unit (100)；And Since neutron-absorbing section (130), first supporting section (110) is extended lengthwise into.
14. the device (1) according to any one of claim 1-11, wherein, first supporting section (110) sets along longitudinal direction Put, and its neutron-absorbing between section (130) across compartmented (120)；The compartmented (120) at least includes perforated pipe (123), to ensure the mechanical connection between neutron-absorbing section (130) and first supporting section (110).
15. the device (1) according to the claims, wherein, the perforated pipe includes multiple mainly extending longitudinally Be open (124), these opening (124) be distributed in the perforated pipe (123) whole profile and the compartmented (120) it is whole On longitudinal size.
16. the device (1) according to any one of claim 1-3, wherein, first supporting section (110) is located at described The vertical direction of neutron-absorbing section (130).
17. the device (1) according to any one of claim 1-3 and claim 16, wherein, in supporting configuration condition Under, first supporting section (110) is located at the vertical direction of the protective case (200) core space (240).
18. the device (1) according to any one of above-mentioned two claim, wherein, first supporting section (110) is being inhaled Receive Longitudinal extending between rod top (101) and neutron-absorbing section (130)；(101) composition activity list at the top of the absorbing rod The upper end of first (100).
19. the device (1) according to any one of above three claim, wherein, the active unit includes pull bar (102), the pull bar at least extends to the neutron-absorbing section (130), described first from the upper end of the active unit (100) Supporting section (110) is the pull bar (102) between the active unit (100) upper end and neutron-absorbing section (130) The bulge-structure (115) of support.
20. the device (1) according to the claims, wherein, the lower end of the bulge-structure (115) helps to form cold But agent thrust face (117), to ensure the supporting of the active unit (100).
21. the device (1) according to any one of above-mentioned two claim, wherein, the bulge-structure (115) is hollow , it is provided with multiple cooling agent taps (116,118).
22. the device (1) according to any one of above three claim, wherein, the bulge-structure (115) is longitudinal direction The cylindrical wall of extension, and second supporting section (210) is the sleeve pipe for being supported or being formed by the protective case (200) inner surface (211)；Space j1 between the bulge-structure (115) cylindrical wall outer surface and described sleeve pipe (211) inner surface is limited For S1 sections.
23. the device (1) according to any of the above-described claim, in addition to active unit (100) damper, for described The dropping process of active unit；The damper includes：
- the first damping piece (140), is supported by the active unit (100) and is set to contact with cooling agent；
- the second damping piece (220), is supported by the protective case (200) and is set to contact with cooling agent；
First damping piece and the second damping piece be arranged so that the active unit (100) fall and under its arrival Fall before the stroke end position under configuration status, first damping piece (140) enters second damping piece (220), then, First damping piece (140) and second damping piece (220) work in coordination to form viscous damper.
24. the device (1) according to the claims, wherein, first supporting section (110) and first damping piece Or second supporting section (210) and second damping piece (220) are supported by same component (112,211) (140).
25. the device (1) according to the claims, wherein, first supporting section (110) and first damping piece (140) or second supporting section (210) and second damping piece (220) or its at least a portion be longitudinal positioning of it is identical Height.
26. the device (1) according to any one of above three claim, wherein, second supporting section (210) and institute It is (112,211) supported by same component to state the second damping piece (220)；The protective case (200) at least includes sleeve pipe (211), the supporting member in the protective case (220) is formed by described sleeve pipe (211).
27. device (1) according to claim 23, described sleeve pipe (211) includes filling the chamber (225) of cooling agent, institute State chamber (225) and form above-mentioned second damping piece (220)；First damping piece (140) forms insert, with described Active unit (100), which is reached, to be inserted the chamber (225) and drives cooling agent before its stroke end position.
28. the device (1) according to the claims, wherein, first damping piece (140) is by being longitudinally disposed at State between active unit (100) bottom (103) and neutron-absorbing section (130), preferably at the active unit (100) bottom At the top of portion (103) and the active unit between (102).
29. the device (1) according to the claims, wherein, second damping piece (220) forms sleeve portion, bag Include chamber (225)；First damping piece (140) forms insert (145), can enter the chamber (225)；The chamber (225) it is circular, with horizontal circular opening (226), is open by these, the insert (145) will be movable single First (100), which are reached, inserts the chamber (225) before the stroke end position under its whereabouts configuration status；The insert (145) A tubule is formd, the formation of its free end has enters chamber (225) beneficial to it by above-mentioned opening (226).
30. the device (1) according to any one of above-mentioned two claim, wherein, second damping piece (220) is by institute State sleeve pipe (211) formation of protective case (200) inner surface support；Second supporting section (210) is by the interior of described sleeve pipe (211) Surface (212) is formed.
31. the device (1) according to the claims, wherein, the chamber (225) is the thickness in described sleeve pipe (211) Formed in degree, the chamber has bottom (227)；Second supporting section (210) is by the inner surface shape of described sleeve pipe (211) Into, it is at least partly longitudinally disposed, towards the chamber (225).
32. the device (1) according to any of the above-described claim, wherein, it is described that the protective case (200) at least includes guiding The guide section (230) of active unit translation.
33. the device (1) according to the claims, wherein, the guide section includes multiple cushion blocks (231), preferably Including three cushion blocks (231), the multiple cushion block is radial, be regularly distributed in the active unit (100) translation shaft week Enclose.
34. the passive reactor shut-off system of heap is answered for core, including the passive triggering type safety device described in any of the above-described claim (1) and assemble mechanism, the assemble mechanism includes the gripping device (300) for active unit (100).
35. the nuclear reactor including reactor core (10) and primary Ioops, the nuclear reactor is at least included as appointed in claim 1-33 Passive triggering type safety device described in one.
36. the nuclear reactor that the claims are limited, is fast neutron reactor.
CN201611047649.4A 2015-11-23 2016-11-23 Passive triggering safety device for nuclear reactors during abnormal coolant reduction Active CN107068213B (en)

Applications Claiming Priority (2)

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FR1561275A FR3044155B1 (en) 2015-11-23 2015-11-23 PASSIVE TRIP SECURITY DEVICE FOR NUCLEAR REACTOR ON ABNORMAL PRIMARY RATE DROP
FR15/61275 2015-11-23

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FR3085531B1 (en) 2018-09-05 2020-10-30 Commissariat Energie Atomique WATERPROOF STRUCTURE FOR ASSEMBLY FOR CONTROL OF THE REACTIVITY OF A QUICK NEUTRON NUCLEAR REACTOR

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JP6948781B2 (en) 2021-10-13
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JP2017096953A (en) 2017-06-01
CN107068213B (en) 2021-11-02
FR3044155B1 (en) 2017-11-10

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