CN1213438C - Reactor system, method of controlling same and means - Google Patents
Reactor system, method of controlling same and means Download PDFInfo
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- CN1213438C CN1213438C CNB008079692A CN00807969A CN1213438C CN 1213438 C CN1213438 C CN 1213438C CN B008079692 A CNB008079692 A CN B008079692A CN 00807969 A CN00807969 A CN 00807969A CN 1213438 C CN1213438 C CN 1213438C
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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
- 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
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- 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
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- 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
- G21C7/107—Control elements adapted for pebble-bed reactors
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- 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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- 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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention relates to a method and a system for controlling and optionally shutting down the power of a nuclear reactor. The control system comprises regulating systems which operate on a neutron-absorption basis and use mobile neutron absorbing bodies. According to the invention a system of holes and channels can be filled with neutron absorbing bodies to a required level by the force of gravity.
Description
Technical field
The present invention relates to the method and the control system that are used to regulate and cut off nuclear reactor power selectively, relate to the nuclear reactor that comprises this system and relate to the neutron absorption object that is used for this adjusting and cuts off nuclear reactor power selectively.
Background technology
Present fission-type reactor comprises reactor core, and this reactor core comprises fuel element.Described fuel element comprises nuclear fuel (uranium isotope, thorium isotope and/or plutonium isotope) and a kind of moderator.Nuclear fission discharges fast neutron, with described fast neutron slowing down, reaching an energy level, thereby causes other fuel generation nuclear fission through moderator.This causes discharging fast neutron again and is used for energy-producing heat.
At least use two independently to cut off system for nuclear reactor is in general very general now.They are used to finish the nucleon chain reaction.At least in these systems can be used in addition regulating operation, that is to say the power and the power features that are used for the conditioned reaction heap.The work of traditional cut-out system be by the material with intercept neutrons be placed on reactor core or reactor core around (for example Zhou Wei reverberator).The quantity of the absorbing agent of putting into must be fully, guaranteeing enough fast adjusting effect and to cut off effect, for example works as temperature change and/or Xe at all normal operating conditions with when breaking down state
135After the decay.
If the system that will cut off also uses on regulating, when normal operation, or not entirely to leave from its active position with these absorbing agents, then when continuing to leave, can improve reaction rate, that is to say and can improve fission rate.Reach the cut-out function by other absorbing agents are moved to active position, therefore stop chain reaction.
So-called high-temperature reactor (HTR) obtains significance recently.Its name draws from the fact, because its graphite-structure has the ability to produce elevated temperature heat.The specific type of HTR is ball heap reactor or ball hill reaction heap.This reactor a series of continuous development phases have been carried out, (pilot reactor work association place is at J ü lich as AVR, Germany, the thermal power of pilot reactor is 46MW and is 850 ℃ of designs to the helium initial temperature, but tentatively runs to 1000 ℃); THTR (thorium-high-temperature reactor; Thermal power be the 750MW place at Uentrop, Germany); Perhaps MODUL-HTR (it is 200MW that the modular ball heap reactor scheme of developing in Germany has thermal power) is known.Ball heap reactor is characterised in that, when its run duration can be put into new spheric fuel element its reactor core and where necessary can be with old taking out from reactor core.These features make regulating system alleviate its task load, have compensated the consumption of nuclear fuel by the taking-up absorber material.The necessary balance of regulating system is owing to temperature change, Xe in these systems
135Concentration change and similar very little reaction fluctuation.
In general in cut-out system and regulating system, use rod, therein absorbing material is enclosed in the metal tube.If correspondingly design ball heap reactor core, it is just much of that in the side reflector of the excellent opening part for this reason arranged that these rods are packed into.Also absorbing agent might be replaced realizing in second cut-out system of MODUL-HTR-scheme as this with the rod sealing with little ball in order to cut off purpose in addition.This ball is known (KLAKs) as " little absorbing agent bead ".These KLAKs are made of the graphite that comprises boron or boron carbide.KLAKs is put into vertical so-called KLAK-opening or KLAK-duct.In general be that these are taken out in the bottom in this KLAK-opening or KLAK-duct by gravity for KLAKs is taken out from its active position.With pneumatic they are sent back in the container in KLAK-duct then.Important difference between the feature of rod and ball is:
1.KLAKs the temperature sensitivity than rod is little.
2. rod is not only from following but also can put into from the top and also can put in different positions when version is stub, and be to concentrate on the bottom in each KLAKs-duct and must to fill or take out downwards therefrom by gravity in order reaching than higher level by gravity KLAKs, to reduce the absorption level.
Up to this point absorber material mainly is to use the form of above-mentioned rod in a lot of reactors, so that influencing the power features curve and particularly check with desirable method inspection influences the thermal power characteristic curve, in general for this characteristic curve leveling.This also appears among the HTR mainly is in order to avoid the high radiation load of local in graphite reactor.In ball heap-HTR, improve the downward concentration of spent fuel.Corresponding power maximal value generally is positioned at the first half of reactor core.If under normal running (operation) conditions, be used for the absorbing agent object of the regulating system of power adjustments and partly be being positioned at part maximum effect position, top near the time, can be with the peaked this variation of the power of top part and therefore the feature that produced or the production of fast neutron are carried out leveling.When the maximum effect position is left, discharge and recover radiation, reduce this radiation and cause cut-out at last and put into more absorber material.In order to utilize this feature of regulating system fully,, in general regulating system is designed to the rod operation still also for cost minimization with this control procedure.At present KLAKs only is used for second cut-out system, that is to say only to be used for cutting off fully.
Up to the present traditional control rod each has the shape of rod, so that around it, arrange material such as boron carbide circlewise by intercept neutrons, and hafnium carbide or similarly annular control object.For example boron carbide is stable when temperature reaches at least 1600 ℃, and the inner metal of rod has lost desired pulling strengrth when temperature surpasses 650 ℃.This has caused trouble, because owing in general good reason arranges these metal bars to such an extent that be suspended on the top, so that can drop to reactor core and absorb to suppress chain reaction and to stop chain reaction selectively fully by improving neutron by gravity.Neutron flux in traditional ball heap reactor is maximum in the upper edge region of reactor core, because fresh fuel element ball is put into reactor core from the top traditionally, and completely or partially consume or the spent fuel ball take out from bottom.Correspondingly the level of neutron flux reduces in reactor from the top down.Therefore to be easy to arrive reactor core from the top be particular importance to the advantage of regulating system.In modern ball heap reactor during in normal operation general temperature reach 900 ℃ and under the operation troubles situation temperature of absorbing agent object can be elevated to 1200 ℃, this has surpassed the tolerance limit of metal bar widely.
Therefore seen the necessity of selecting the approach different with traditional absorbing agent rod in regulating system and cut-out system, this can overcome or reduce traditional excellent thermo-responsive problem not losing under regulating power and the protective reaction pile radiation event of overload.
Summary of the invention
The present invention has considered a nuclear reactor, nuclear reactor comprises that absorbing object of which movement by neutron carries out being used for power adjustments and cutting off the regulator system of regulating on the basis that neutron absorbs, regulator system comprises the channel system of the device that has the duct or have the hole therein, these maybe can be loaded into adjustable height with a series of absorption objects loadings that fall by gravity, absorb object this moment a sectional dimension, this has enough gaps of easy sliding relation corresponding to the sectional dimension in duct in principle and absorbs object is downwards stent support by determining height at least.
At the support of determining height with absorb the longitudinal direction that the baffle plate body that the slip ability will one or morely be arranged between the object valuably equally is placed on the duct, above-mentioned therein baffle plate body is compared not with the neutron receptivity of absorption object or the neutron receptivity that reduces is arranged.Useful is that each duct comprises a lot of above-mentioned baffle plate bodies.
The baffle plate body can be different neutron receptivities, says that more accurately the neutron receptivity of baffle plate body reduces downwards.
If one or more baffle plate bodies can have the characteristic of reflected neutron selectively, if for example they are enclosed in the reflected neutron material or during orientating reflex neutron material.
According to special form of implementation piston rod is used as the support of determining height.Typical piston rod comprises piston or piston-shaped.What the highway section of the baffle plate body process between the support of neutron absorption object and piston rod or other take the altitude really was useful is, all run locations of piston are below the reactor core minimum altitude, that is to say in radiation, particularly minimum the or non-existent zone of neutron flux.Useful is handles (that is to say raise or fall) with piston by the suitable operating control of reactor pressure vessel outside.This operating control can be mechanical, hydraulic pressure, or combination electromagnetism or two or more methods.
Piston or piston rod can be by the material that is suitable for purpose such as graphite, potteries, and for example aluminium oxide or beryllia or a kind of suitable metal such as electric steel constitute.
Absorbing object can move under the gravity situation, up to by piston rod or determine that in addition the support of height exists the fact utilization that it stops, for example since under the current interruptions reactor operation failure condition under normal circumstances by automatic release plunger bar or automatically release action determining that in addition anchorage force on the height bracket will absorb object and drop to its off-position (that is to say the place of the maximum neutron flux of appearance) automatically.This can carry out with the power that traditional method supports the elevated position of determining support height by automatic release, for example by discharging electromagnetic clutch or discharging bracing or strutting arrangement.
The baffle plate body can by have be suitable for machinery, heat or other characteristic purposes do not absorb or the material of weak intercept neutrons constitutes.Employed material might be same or be similar to the material of above-mentioned piston or piston rod, however useful be nonmetal.
Not only will absorb object but also the baffle plate body is shaped like this and design, making it is can not being stuck in the duct of being free to slide.
Significant advantage is, the present invention provides by feature, be that the duct has comprised the single rod that the column of the single body that do not link together replace to link up and since the duct be not must be everywhere straight line and bending can be arranged, object can not entered in the duct with blocking.In general only be necessary that the trend in duct is at gravity direction.
The shape that absorbs object and baffle plate body for above-mentioned purpose can have right cylinder chamfered edge or fillet from the process ellipsoid or barrel-shaped the changing to of sphere.In use useful is packs the elongate objects of final form in its duct separately into according to its length.The radius-of-curvature of contingent bending has limited the axial length of object in the duct, and in fact length for example can be 1 to 5 times of channel diameter, and useful is 1 to 3 times, and reasonable is 1 to 2 times of variation.Other details can be with reference to the instructions of following object.
This deviation of duct linearity can be utilized, and neutron absorbs object near reactor core and the neutron absorption that therefore changes the intercept neutrons object on different core heights.The duct device can be utilized, and the trend in different ducts interrelates with reactor core can different bendings.It can be straight line that a few ducts are arranged, and that is to say with reactor core has identical distance, and some other duct can be crooked, is directed on the differing heights that is toward or away from reactor core further so that will absorb object.This principle is similar to us simultaneously as the application 98/0128 of annex.The application's principle and the principle of application in the past might be combined in addition, according to former application was with a collection of KLAKs or similar free-pouring absorption object, that is to say that useful is the diameter that absorbs ball can be designed to be no more than 1/6 of minimum channel diameter.
The duct can have unified circular section at it above the whole length.Yet as the situation of the patented claim 98/0128 in South Africa might use the duct in rectangle or microscler cross section will absorb object and in case of necessity the baffle plate body combine, the respective cross-section in its each duct is in order easily to endwisely slip in the duct and suitable gap is complementary therein, with such equipment, in the zone of closing on the reactor core part, maximum neutron flux occurs there when normal operation, the cross section bearing of trend in duct is perpendicular to the reactor core axis.
Might add or be attached to selectively on this duct, this is crooked in the zone of axially leaving reactor core/reverberator critical surface, reactor core radiation therein reduces under normal operation, can there be axial torsion gradually in this duct with microscler cross section, and the direction radial finger that extends up to the regional cross section with the reactor core radiation that normally reduces is to the reactor core axis.
Additional or be attached to above-mentioned might the maximization in high reactor core radiation areas selectively by means of the neutron flux layout that the present invention will absorb object and/or baffle plate body, if people use the duct in these zones for these objects, it is the part opening that the reactor core zone is closed in these ducts.We with the meaning of " part opening " be the existence of open area be form with slit or a series of slit or opening constitute with the reactor core parallel axes and be design like this, to absorb object and/or baffle plate body remains in the duct and particularly can not arrive the duct under ball heap reactor situation.
Useful is the operating control of piston rod or the outside that drive unit is positioned at reactor pressure vessel.Corresponding maintenance work on these devices can be carried out without difficulty.Operating control or drive unit can or similarly be connected with piston rod through connecting rod, wherein have only small through hole need include suitable encapsulant by pressure vessel wall.Be easy to operating control or drive unit in pressure vessel are not precluded within protection scope of the present invention.
The reactor neutralization that the present invention is applied in valuably high-temperature reactor (HTR)-type particularly is applied in the reactor, the operation of this reactor is designed to, the fresh nuclear fuel of the fuel of the partial combustion that will have or not return is at one end put into and will be had or not have the spent fuel of the fuel of partial combustion to take out at an opposite end, therein neutron being absorbed object is kept in the device, this device is suitable for directly leaning against or playing maximum absorption near the zone of reactor core segment, reach maximum or approaching maximum power by reactor fuel there, with directly or play the effect that reduces or zero neutron absorbs near the zone of reactor core part, the fuel radiation reduces there.Useful form of implementation is the type of ball fuel assembly or the type of ball heap.
Height (interrelating with reactor core) on given reactor should take place from the absorption maximum effect to fewer absorption effect thereon or the variation of zero absorption effect, farthest depends on how fuel is inputed to reactor.Useful is device should be directly or play absorption maximum or play near the zone of reactor core the first half and reduce or zero effect that absorbs near the absorption maximum effect with in a zone, half that not have there that the core power of poisoning is approximately the peak power zone is to 1/3rd.Accurately some say that zone that reduce or zero absorption starts from being not less than 1/10 of whole core height above the reactor zone, ground of reactor.
If relate to reactor with multilayer fuel handling capacity, the peak power of reactor core zone generally whole core height 50% and 70% between and device with absorption maximum effect partly extend downwardly into 30% of whole core height above the reactor zone, ground that is lower than reactor.
If relate to reactor on the contrary with one way feeding (OTTO), the peak power of reactor core zone generally whole core height 66% and 75% between, the device zone that has the absorption maximum effect therein extends downwardly into 40% height of whole core height above the reactor zone, ground that is not less than reactor.Accurately some say that the device zone with absorption maximum effect extends downwardly into 50% the height that is not less than on reactor zone, the ground of reactor whole core height.
The present invention needs high initial temperature therein when the turbine that directly energy work rate is used in operation helium turbine or other gas shape media, and special benefit is arranged.
Arranged to carry out the method that nuclear reactor power is regulated by means of the object intercept neutrons of intercept neutrons according to the other appearance form of the present invention, this method may further comprise the steps:
-be applicable to the charging of the regulating system of conditioned reaction heap power, comprise the channel system of device with this regulating system with duct or hole, have a series of neutrons that are positioned on the inclined-plane by gravity and absorb object, its sectional dimension is corresponding to the cross section, duct (hole) of the channel system that is free to slide enough gaps: and
-adjust the height that neutron absorbs object by the adjustable machinery mount below object.
Remaining feature is suitable for this method equally with the above-mentioned details relevant with reactor.
The present invention continues to extend on the reverberator of nuclear reactor, and the channel system that has duct or aperture apparatus therein is used for bearing and absorbs object by neutron and pile the cross section of stamping the column that constitutes and duct (hole) up and down and be free to slide in duct (hole) for object corresponding to the cross section of bearing the certain object in duct in principle and have enough gaps.
Above-mentionedly especially also be suitable for reverberator with the key character in the relevant duct of narrating of reactor and affiliated device.
Protection scope of the present invention extends to above-mentioned absorption object and the baffle plate body that is suitable for use in according in method of the present invention and the reactor in addition.The present invention has arranged neutron to absorb object and baffle plate body like this, be in contact with one another slidably in these ducts in being formed in nuclear reactor, therein the baffle plate body with absorb compare zero receptivity or the neutron receptivity that reduces and above-mentioned object of object cross section corresponding to the cross section, duct arranged in principle, these objects are born in the duct during use, have enough gaps in order to be free to slide in the duct.
These absorb objects has significant difference with the KLAKs of up-to-date technology level on its size.Its size of the axial length orientation measurement in duct useful be 40mm to 400mm, relatively good is 50mm to 220mm, is preferably 60mm to 150mm.
The sectional dimension that absorbs object and baffle plate body depends on whether the duct is columniform microscler or other shape.If object is spherical, the above-mentioned scope of diameter is fit to, and wherein diameter preferably approaches lower limit.If the duct is columniform, the cross section of object is corresponding to the cross section, duct with gap.Object axial structure can be from the process of sphere ellipsoidal or barrel-shaped to having the cylindrical of end fillet or chamfered edge.Amplify if for example object should have been improved the special area of receptivity, the surface configuration of amplifying can be covered on the surface that is suitable for above-mentioned basic configuration, for example have the ripple pattern in alternately protruding and recessed zone.
Size relatively short when microscler cross section for example can be in 20mm to 100mm scope, and useful is at 30mm to 80mm, for example is that 60mm and long size can be from 100mm to 300mm scopes, and useful is at 150mm to 280mm, for example is 260mm.Short side can have circular, for example semi-cylindrical structure.Longitudinal direction at object that is to say the direction of motion passing hole channel, be suitable for same principle as above save narration the object exception with circular section be to be a kind of form of attenuation of longitudinal section that is parallel to the long side of lateral cross section perpendicular to the longitudinal axis cross section of the long side of lateral cross section.
Absorb object can have do not absorb or weak absorption for example by the reactor core of graphite or refractory ceramic material, reactor core (being orientating reaction heap reactor core at least when needing) has the material of strong intercept neutrons as boron carbide or hafnium carbide coating or covering.
With aforesaid baffle plate body also as a part of the present invention and useful be to have same size (perhaps same at least sectional dimension) to absorb object as neutron.The baffle plate body can be with the neutron reflection material as using special quality equadag coating or covering.
As the other appearance form of the present invention is to have arranged graphite block or graphite brick, these and reactor reflector group are fitted together and the duct that can have the neutron absorption object of new feature therein as above-mentioned formation, and particularly aforesaid duct is an opening closing on reactor core.Therefore graphite block or graphite brick are shaped like this, design and structure can make itself and reactor reflector group be fitted together.
In the reactor system of newtype, the dosage or the concentration of hitting the fast neutron on the reverberator inwall can be brought up to above 1.5 * 10
22Cm
-2(EDN) numerical value.Therefore reach 900 ℃ or higher in view of above-mentioned modernized temperature, the sidewall reflectors with the flat surface that runs through reach its designed life that is approximately 30 years also can be malfunctioning before the expectation value.This is that graphite stereomutation process is divided two stages because of the reason of the graphite stereomutation that is determined by radiation.Cause volumetric contraction without a doubt in first stage neutron irradiation.And second stage volume amplifies, and might surpass original size this moment and cause mechanical load to damage reactor.In order to alleviate or to overcome this problem, use a kind of method slaking with pointing to the inner reflector surface and the respective surfaces of graphite block or graphite brick valuably according to the present invention, this change in size of this well-known own balance, this change in size are that graphite is subjected to after relatively for a long time stronger neutron irradiation.
Description of drawings
On additional schematic diagram basis, continue narration the present invention below without restriction.Expression in the accompanying drawings:
Accompanying drawing 1 is according to the longitudinal section sketch of the modularization HTR-ball heap types of nuclear reactor of the present invention's exploitation;
The cross-sectional of the part in the duct that accompanying drawing 2 and 3 prepare to use by nuclear reactor can be given these ducts charging, radial section and reactor core journal offsets at this moment by a series of absorption objects that fall by gravity;
Accompanying drawing 4 has the cylindrical bore perpendicular to three straight lines of reverberator and reactor core critical surface back according to the three-dimensional oppositely simplified cross-sectional view of the reflector sections of nuclear reactor of the present invention;
Accompanying drawing 5 is according to the three-dimensional oppositely simplified cross-sectional view of nuclear reactor reflector sections of the present invention, three ducts of reversing of having arranged to have in principle microscler cross section therein in reverberator perpendicular to the critical surface of its back of reactor core;
Accompanying drawing 6 constitutes three ducts longitudinally therein according to the part sketch of the reverberator of nuclear reactor of the present invention, its expansion structure is illustrated on the accompanying drawing 4, and wherein to close on the reactor core of reactor be opening partly in each duct;
The amplifier section view sketch of the part in the duct that accompanying drawing 7 is represented on accompanying drawing 6;
Accompanying drawing 8,9,10 and 12 use the neutron assimilate side with circular section in having the duct of about corresponding circular section to look sketch;
Accompanying drawing 11 or 13 is in the XI-XI cross section of accompanying drawing 10 with at the top view of the XII-XII cross section of accompanying drawing 12 object;
Accompanying drawing 14,15,16 and 18 use the neutron assimilate side in microscler cross section that has in principle in having about duct, corresponding microscler cross section to look sketch;
Accompanying drawing 17 or 19 is in the XVII-XVII cross section of accompanying drawing 16 with at the top view of accompanying drawing 18XIX-XIX cross section object;
Accompanying drawing 20 has the cross-sectional of the equadag coating baffle plate body of reactor core and reflection;
The diagrammatic cross-sectional view of the part of accompanying drawing 21 nuclear reactor reverberators, the cross section also absorbs by the neutron that is placed on the duct that constitutes in the reverberator that object passes through and by the fuel element in reactor core therein;
Accompanying drawing 22 is by the longitudinal cross-section sketch of the following part (being masked as XXII) of the reactor of accompanying drawing 1 expression;
Accompanying drawing 23 and 24 is by having the baffle plate body and absorb the longitudinal component cross-sectional in one section in duct of two kinds of particular arrangement of object, and this is two special run locations decisions that act on the piston rod on the object from the bottom, duct.
Embodiment
In general 30 representatives of the reference number on accompanying drawing improve according to foregoing invention and the parts of ball heap (ball the fuel assembly)-HTR-reactor of the MODUL-HTR-type of development.Reactor 30 comprises the reactor core 32 of fuel being filled taper top height 34.Reference number 36 represents surf zone within it by high purity graphite and the reverberator that is made of low-quality graphite in its perimeter.Reactor core 32 and reverberator 36 be by reactor vessel or pressure vessel 38 with cooling air for example the helium connecting pipe 40 that offers reactor core 32 be connected and be closed.Reference number 42 general proxy fuel inlets and reference number 44 are the fuel outlets by 46 controls of outlet regulating device.The following part of reverberator is represented with reference symbol 48.
On accompanying drawing 22 to 24 bases by the support of piston rod 58 forms of determining height with object 52,54,56 remain on down direction, wherein each has the piston 59 that makes the object indentation.These features will be described in detail below.
Up to the present traditional MODUL-HTR-reactor is to regulate with first cut-out system of the neutron absorbing rod of metal absorbing rod and sealing and regulating system and second cut-out system, and this is to use little absorption ball (KLAKs) work fully.Replace by above-mentioned control system or replenish according to first cut-out system of the present invention and regulating system and/or second cut-out system.
The duct 50 of some conditioned reactions heap power has special configuration, and 3 and 5 couples of wherein two describe with reference to the accompanying drawings.Carrying neutron to absorb neutron degree of absorption that object reached in the duct depends in duct on the height of determining near or far away and depend on the angular width that on definite height duct offers reactor core with reactor core.As top, narrated, a series of height that belong to reactor core had been arranged, determined the boundary of duct height on the one hand, and under the service condition of determining on this height, must carry out regulatory function to a certain degree.Height is along with the reactor operation mode changes.In the reactor core zone, maximum therein neutron flux needs maximum absorption in the highest flight and in order to regulate, and the duct is designed to the absorption maximum effect, and near the zone of reactor core, the absorption effect that occur to reduce there or neutron flux do not occur, that the duct is configured to reduce.In general the duct device directly or play maximum or near maximum absorption effect near the top part of reactor core (by reference number 60 expressions).Absorption effect reduces or becomes zero on the following part in reactor core zone is lower than by the corresponding height in the zone of reference number 60 expressions.
The whole core height of reference number 62 expression reactor cores 50% and 70% between a zone, occur maximum neutron flux therein and therefore require maximum absorption effect.Reference number 64 is illustrated in 30% height of core height above the ground return device zone 48.Zone with absorption maximum effect generally extends to and is not less than 30% of core height 64.If the reactor of operation one way feeding (OTTO), the peak power zone of reactor core generally whole core height (by reference number 66 expression) 66% and 75% between height extend to any one height that lower height surpasses 40% (by reference number 68 expressions) of core height.
If in addition on the one hand reactor is repeatedly used the fuel supplement feeding, the fuel objects (for example fuel sphere or fuel element) that take out through outlet 44 from reactor core are analyzed and are determined its burning degree.Before being replaced by new fuel object, it it can be sent back to 20 times in this way.The reactor core peak power generally is positioned on the height between half (following ends of regional 60) of 2/3 (bottoms in zone 66) of reactor core height and pile height in the reactor of like this operation.
The height of the whole core height 1/10 of reference number 70 expressions.Generally have minimizing or zero absorption effect zone from this height upward to corresponding than higher height (as discussed above), maximum absorption appears there.
For the necessity that reaches on receptivity changes, can there be different configurations in duct of the present invention along its length.
People see a kind of configuration in duct 50 on accompanying drawing 3 bases like this, therein at down direction by with the duct tilting raising that causes absorption effect to reactor core 32 downwards.Duct 50 turns back to location longitudinally then again.Bending 72 along oblique orifice throat length is round, so that reduce to absorb object and the slip of baffle plate body in the duct, with the radius-of-curvature of bending be design like this on the basis in vertical highway section of the absorption object that perhaps in the duct, uses and baffle plate body, make object can freely overcome bending.There is a circular section in the duct 50 of expression in order to use absorption object and baffle plate body with corresponding circular section on accompanying drawing 2,3 and 4.
As finding out that from accompanying drawing 5 there is axial torsion gradually in the duct, this reaches the cross-sectional length direction radially in the configuration of reactor core axis (seeing accompanying drawing bottom) from duct cross-sectional length direction perpendicular to the configuration of reactor core axis (seeing the accompanying drawing top).This axial torsion has corresponding effect for duct and the receptivity that the absorption object that belongs to the duct reaches.Longitudinal direction perpendicular to the local receptivity of reactor core journal offset (with the reactor core tangentially) than higher.Such configuration is the part near reactor core, occurs maximum neutron flux there when normal operation.The relative reactor core in opposite duct has the angle that reduces area, and the longitudinal direction in duct is radially in the reactor core axis there.Such configuration is to be suitable for having the radioactive zone of the neutron flux that reduces under the normal condition.
Though not expression on accompanying drawing 5, the skew of the linearity in the duct of axial torsion (gradient) can prolong, so that improve or change the absorption characteristic in duct.
By using duct 50 to improve, this closes on reactor core territory 32 is openings partly in high nuclear activity zone for a kind of form of implementation of having represented reverberator 36 on the basis of accompanying drawing 6,7 and 21, the neutron flux layout that absorbs object and baffle plate body thereon.The form of implementation of representing on these accompanying drawings constitutes unique longitudinal slot 74 along the part of each duct 50 length.The slit is parallel to the reactor wire mandrel and extends from the back passing hole channel 50 in reactor core zone, as what particularly see from accompanying drawing 7.Two mutual aspectant graphite bricks or graphite block 76 are to be shaped like this and design, constitute the part in slit 74 and constitute duct 50 between them.As finding out from accompanying drawing 21, slit 74 is such shapings and designs, and will absorb object and/or baffle plate body 52 and remain on the duct neutralization particularly like this, makes fuel sphere 78 (during ball heap reactor situation) impossible arrival duct.
Brick or piece 76 as the expression of having narrated in accompanying drawing 6,7 and 21 constitute the slit, and extend on the whole vertical length of brick or piece in this slit.Yet (do not have expression) constitutes the graphite brick of reactor or graphite block each has discrete slit in the other form of implementation of the present invention, and brick that vertical stacks is stamped or piece arrangement constitute the slit of following mutually that has the series of discrete of opening for the duct of determining 50 like this.As from accompanying drawing 7 and 21, finding out, be slaking towards the brick of reactor core or the surface 77 of determining, so that the size of graphite is through the change in size of balance graphite after the relatively more long strong neutron irradiation.
If we rotate back into accompanying drawing 8 to 13, represented to have the spectrum of circular section neutron assimilate shape therein.The part that described shape reaches the shape continuous spectrum with right cylinder rounding or chamfered edge (accompanying drawing 12 and 13) from sphere (accompanying drawing 8) through barrel-shaped (accompanying drawing 9) and ellipsoid (accompanying drawing 10 and 11).Select to absorb the diameter of object 52 in the following manner, make them, under action of gravity, be enough to make object in the duct, to be free to slide corresponding to the diameter that is placed into the duct.
Absorbing object 52 has typically reactor core by not absorbing of constituting of graphite or refractory ceramic material or weak absorption, and this is the shell that the sub-absorbing material of persistent erection such as boron carbide or hafnium carbide are coated or covered.The object that is orientating reaction heap reactor core in use in some forms of implementation that absorb object partly is to cover with such shell.
The absorption object 54 of on accompanying drawing 14 to 19 bases, having represented to have general microscler cross section.The size relatively short at this object upper section changes to 100mm from 20mm, and useful is is positioned at 30 to 80mm (for example 60mm) and long size can be positioned at from 100mm to 300mm, and useful is to be 150mm to 280mm (for example 260mm).Minor face as the cross section seen has the fillet configuration, then particularly on accompanying drawing 18 the axial limit of the absorption object of expression corresponding to cross section with half-cylindrical configuration.Absorbing object 54 has the syndeton that is similar to object 52 and comprises weak reactor core that absorbs and the shell that comprises by the sub-absorbing material of persistent erection.
Though not expression on accompanying drawing 8 to 19 absorbs in the certain form of implementation of object for improving receptivity at neutron the surface configuration of amplifying (for example have alternately projection with ripple model recessed zone) is covered on the basic configuration of object.The length of the object of measuring in the axial length direction (being x on accompanying drawing 2) in duct 52,54 is positioned at 40 valuably to 400mm, relatively goodly is 50 to 220mm and is preferably 60 to 150mm.The axial length of object is changed to 1 to 5 times of diameter in duct in different forms of implementation, be typically 1 to 3 times and useful be 1 to 2 times.
In general the reference number 56 of expression is the baffle plate body on accompanying drawing 20.The object of expression has a circular section on accompanying drawing 20.Yet in fact the baffle plate body can be arranged to the Any shape that neutron absorbs object 52,54 (as expression in accompanying drawing 8 to 19).Baffle plate body and neutron absorb object and use same sectional dimension, yet can change on the length that absorbs object.Each baffle plate body 56 comprises an interior reactor core 80, this be for example coat with the shell of reflected neutron material with high-quality special graphite or cover.
We turn to the accompanying drawing 22 to 24 of expression piston rod 58 (comprising piston 59) operation now.The effect of piston rod is as the support of determining height, and neutron absorbs 56 of object 52 and baffle plate bodies thereon.The highway section in that piston and neutron absorb between the object 52 that is occupied by baffle plate body 56 is chosen such that piston rod and piston are positioned at below the minimum altitude of nuclear reactor all the time, and particularly neutron flux is minimum or do not exist to that is to say therein ray.
As finding out from accompanying drawing 22, piston is handled (that is to say and raise or reduction) by hydraulic control unit 86.(not expression) operating control can be mechanical, pneumatic in other forms of implementation of the present invention, the combination of electromagnetism or two or more this methods.The outside that operating control 86 is positioned at reactor pressure vessel 38 is easy to safeguard.Operating control 86 is to be connected with piston rod 58 through connecting rod 88 (accompanying drawing 22), therein connecting rod is guided by the little opening on pressure vessel 38 walls 90, and little opening seals with suitable seal device 92.The operating control and the drive unit that (do not have to represent) piston rod in the other form of implementation of the present invention are to be positioned at reactor pressure vessel 38 inside.
The object 52 and the baffle plate body 56 of intercept neutrons move under action of gravity, if they are not when being blocked by piston rod 58.Then move disturbed conditions for example because current interruptions drops to its off-position (for maximum absorbance capacity, maximum there neutron flux in the highest flight) with reactor shut-down automatically by absorbing object 52 at reactor 30.The automatic decline that absorbs object can be undertaken by the anchorage force that acts on the piston rod 58 under the automatic release normal condition.Arrange by electromagnetic clutch or support fixture 94 in accompanying drawing 22 upper support power, this is released when current interruptions.Represented that on accompanying drawing 24 neutron absorbs object 52 in its off-position, wherein piston 59 is positioned at the lower end in duct 50.Neutron absorbs object 52 and is positioned at adjusting position on accompanying drawing 23 on the contrary, this adjusting position vertically can be changed by improving or reduce piston 59 in order to control purpose.
Though be not shown on the accompanying drawing, in general can utilize the device in duct 50, different thereon ducts is different with getting in touch of reactor core 32.Also some ducts can be designed for moving a collection of KLAKs or similar free-pouring assimilate style as having the absorption ball that is no more than minimum channel diameter 1/6 diameter.Can will not only comprise neutron absorption object 52,54 and comprise the duct of baffle plate body 56 and have unique regulating system of the subset of cell channels synthetic reaction heap of KLAKs separately like this.
Following claims are ingredients that the present invention declares.
Notion " being comprised " and different grammatical modification is interpreted as " comprising " in the application of above-mentioned instructions and in claims on its free meaning, therefore is not adopt the feature of clear and definite reference and point to be included except clear and definite above-mentioned feature and point.
(with reference to the accompanying drawings) reference number of narrating in claims is in order to carry out the feature that illustrates among all digital with the excellent embodiment in claims relevant with comparalive ease, if yet when the clause of claims is not subjected to accompanying drawing to represent to limit with any method, from the context of article, tangible contradiction can not occur.
Claims (9)
1. nuclear reactor (30),
-have a control system to be used for regulating and/or cutting off nuclear reactor power,
-have a duct (50) at least one vertically extending reflector walls (36) that is arranged in nuclear reactor fully,
It is characterized by,
Described nuclear reactor,
-have at least one neutron to absorb object (52,54), described neutron absorbs object (52,54) gravitate ground and is positioned at inside, duct (50) level height of fixed piston bar (58) really, and its sectional dimension corresponding to the sectional dimension of duct (50) and
-have an operating means that is used for promoting and reducing piston rod (58).
2. the nuclear reactor that requires according to aforesaid right has hydraulic means as the operating means that promotes and reduce piston rod (58).
3. require 1 or 2 nuclear reactor according to aforesaid right, therein
A plurality of ducts are arranged in circlewise in the reverberator of nuclear reactor.
4. require 1 or 2 nuclear reactor according to aforesaid right, therein
Absorb arrangement baffle plate body (56) between object (52,54) and the piston (59) at neutron.
5. absorb object (52 by neutron, 54) method of adjusting and/or cut-out nuclear reactor (30) power, therein, in the vertically extending duct of in the nuclear reactor reverberator at least one (50), at least one neutron absorbs object (52,54) and is raised and reduces from the exercisable piston rod of bottom (58) by one.
6. require 5 method according to aforesaid right, therein,
Neutron is absorbed object (52,54) to have in the zone of maximum neutron flux at nuclear reactor and moves.
7. require 5 or 6 method according to aforesaid right, therein
Absorb arrangement baffle plate body between object (52,54) and the piston (59) at neutron.
8. require 5 or 6 method according to aforesaid right, therein
During regulating piston, piston (59) is rested on the bottom of nuclear reactor region of activation.
9. require 5 or 6 method according to aforesaid right, therein
By the described piston rod of hydraulic means vertical moving (58).
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| ZA99/02247 | 1999-03-23 | ||
| ZA9902247A ZA992247B (en) | 1999-03-23 | 1999-03-23 | Reactor system and control method and means. |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN1367928A CN1367928A (en) | 2002-09-04 |
| CN1213438C true CN1213438C (en) | 2005-08-03 |
Family
ID=25587637
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CNB008079692A Expired - Fee Related CN1213438C (en) | 1999-03-23 | 2000-03-21 | Reactor system, method of controlling same and means |
Country Status (4)
| Country | Link |
|---|---|
| EP (1) | EP1171886A2 (en) |
| CN (1) | CN1213438C (en) |
| WO (1) | WO2000057426A2 (en) |
| ZA (1) | ZA992247B (en) |
Families Citing this family (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US9852818B2 (en) | 2009-11-06 | 2017-12-26 | Terrapower, Llc | Systems and methods for controlling reactivity in a nuclear fission reactor |
| CN102714063B (en) * | 2009-11-06 | 2016-06-22 | 泰拉能源有限责任公司 | For controlling the reactive system and method in nuclear reactor |
| US9190177B2 (en) | 2009-11-06 | 2015-11-17 | Terrapower, Llc | Systems and methods for controlling reactivity in a nuclear fission reactor |
| US9793013B2 (en) | 2009-11-06 | 2017-10-17 | Terrapower, Llc | Systems and methods for controlling reactivity in a nuclear fission reactor |
| WO2016109798A1 (en) * | 2014-12-31 | 2016-07-07 | Terrapower, Llc | Automatic hydropneumatic actuation device |
| CN113053546A (en) * | 2021-03-12 | 2021-06-29 | 中国核电工程有限公司 | Horizontal gas-cooled micro-reactor control rod and horizontal reactor core system |
Family Cites Families (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR1258757A (en) * | 1960-06-08 | 1961-04-14 | Beteiligungs & Patentverw Gmbh | Switch-off device for nuclear reactors |
| DE3242760A1 (en) * | 1982-11-19 | 1984-05-24 | Hochtemperatur-Reaktorbau GmbH, 5000 Köln | Method for shutting down a high-temperature reactor having a pebble bed |
| DE3601750A1 (en) * | 1986-01-22 | 1987-07-23 | Hochtemperatur Reaktorbau Gmbh | CERAMIC INSTALLATIONS |
| DE3601747A1 (en) * | 1986-01-22 | 1987-07-23 | Hochtemperatur Reaktorbau Gmbh | SWITCHING OFF A HIGH TEMPERATURE REACTOR |
| DE3603091A1 (en) * | 1986-02-01 | 1987-08-06 | Hochtemperatur Reaktorbau Gmbh | Gas-cooled HT small reactor having a core made from a bed of spherical fuel elements |
-
1999
- 1999-03-23 ZA ZA9902247A patent/ZA992247B/en unknown
-
2000
- 2000-03-21 WO PCT/DE2000/000899 patent/WO2000057426A2/en not_active Application Discontinuation
- 2000-03-21 CN CNB008079692A patent/CN1213438C/en not_active Expired - Fee Related
- 2000-03-21 EP EP00925053A patent/EP1171886A2/en not_active Withdrawn
Also Published As
| Publication number | Publication date |
|---|---|
| CN1367928A (en) | 2002-09-04 |
| WO2000057426A2 (en) | 2000-09-28 |
| WO2000057426A3 (en) | 2001-04-05 |
| ZA992247B (en) | 2001-01-31 |
| EP1171886A2 (en) | 2002-01-16 |
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